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Sample records for phenix end-of-life thermal-hydraulic

  1. Pre-analysis of Phenix End-of-Life Thermal-hydraulic tests with the MARS-LMR Code

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Kwon, Young Min; Chang, Won Pyo; Suk, Su Dong; Lee, Yong Bum

    2009-01-01

    A prototype SFR, PHENIX has been operated by the French Commissariat a l'energie atomique (CEA) and the Electricite de France (EdF) since 1973. Through the successful operation for 35 years, PHENIX has achieved its original objective to demonstrate a fast breeder reactor technology and also played an important role as an irradiation facility for innovative fuels and materials. Since its first operation, PHENIX has accumulated about 4,300 equivalent full power days (EFPDs) of operational experience and it reached its final shutdown in 2009. Before the decommissioning of PHENIX, the CEA started a PHENIX end-of-life (EOL) test program and opened it for international collaboration to share the valuable information from the test. The KAERI joined this program to utilize the unique opportunity to validate its SFR system analysis code, MARS-LMR which will be a basic tool in future SFR development

  2. Recent Analyses of Phenix End of Life Tests and Perspectives

    International Nuclear Information System (INIS)

    Fontaine, B.; Martin, L.; Prulhière, G.; Eschbach, R.; Portier, J.-L.; Masoni, P.; Tauveron, N.; Bavière, R.; Verwaerde, D.; Hamy, J.-M.

    2013-01-01

    Conclusion: • End of Life tests performed at PHENIX in 2009 gathered a lot of information concerning thermalhydraulics, core physics and fuel behavior in SFR cores. • The analysis of these tests is still undergoing for some of them, involving international collaborations. • To better understand the measurements, complex models are developed thanks to recent computer science progress: • thermalhydraulics: coupling CFD and system codes neutronics: - perturbation theory applied to Bateman equations - model of distorted core; • mechanics: fluid-structure interaction. The test results allow to validate these developments, which could be applied in the future for new SFR design

  3. Multi-dimensional approach of MARS-LMR for the analysis of Phenix End-of-Life natural circulation test

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Chang, Won Pyo; Lee, Kwi Lim

    2012-01-01

    Phenix is one of the important prototype sodium-cooled fast reactors (SFR) in nuclear reactor development history. It had been operated successfully for 35 years by the French Commissariat a l'energie atomique (CEA) and the Electricite de France (EdF) achieving its original objectives of demonstrating a fast breeder reactor technology and of playing the role of irradiation facility for innovative fuels and materials. After its final shutdown in 2009, CEA launched the Phenix End-of-life (EOL) test program. It provided a unique opportunity to generate reliable test data which is inevitable in the validation and verification of a SFR system analysis code. KAERI joined this international collaboration program of IAEA CRP and has performed the pretest analysis and post-test analysis utilizing the one-dimensional modeling of the MARS-LMR code, which had been developed by KAERI for the transient analysis of SFR systems. Through the previous studies, it has been identified that there are some limitations in the modeling of complicated thermal-hydraulic behaviors in the large pool volumes with the one-dimensional modeling. Recently, KAERI performed the analysis of Phenix EOL natural circulation test with multi-dimensional pool modeling, which is detailed below

  4. Multi-dimensional approach of MARS-LMR for the analysis of Phenix End-of-Life natural circulation test

    Energy Technology Data Exchange (ETDEWEB)

    Jeong, Hae Yong; Ha, Kwi Seok; Chang, Won Pyo; Lee, Kwi Lim [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    Phenix is one of the important prototype sodium-cooled fast reactors (SFR) in nuclear reactor development history. It had been operated successfully for 35 years by the French Commissariat a l'energie atomique (CEA) and the Electricite de France (EdF) achieving its original objectives of demonstrating a fast breeder reactor technology and of playing the role of irradiation facility for innovative fuels and materials. After its final shutdown in 2009, CEA launched the Phenix End-of-life (EOL) test program. It provided a unique opportunity to generate reliable test data which is inevitable in the validation and verification of a SFR system analysis code. KAERI joined this international collaboration program of IAEA CRP and has performed the pretest analysis and post-test analysis utilizing the one-dimensional modeling of the MARS-LMR code, which had been developed by KAERI for the transient analysis of SFR systems. Through the previous studies, it has been identified that there are some limitations in the modeling of complicated thermal-hydraulic behaviors in the large pool volumes with the one-dimensional modeling. Recently, KAERI performed the analysis of Phenix EOL natural circulation test with multi-dimensional pool modeling, which is detailed below

  5. Consultants’ Meeting (Preparatory Meeting) on the IAEA Coordinated Research Project (CRP) “PHENIX End-of-Life Tests”. Working Material

    International Nuclear Information System (INIS)

    2008-01-01

    The overall objective of the CRP is to improve/validate the Member States' analytical capabilities in the field of fast reactor simulation and design. A necessary condition towards achieving this objective is a wide international verification and validation effort of the analysis methodology and codes currently employed in the fields of fast reactor neutronics, thermal hydraulics and plant dynamics to achieve enhanced safety. Therefore, in providing the required wide international basis of interested Member States, each applying different methodologies, the CRP will contribute towards achieving the stated objective with the help of benchmark exercises focusing on the experimental results obtained during the planned PHENIX End-of-Life (EOL) Tests

  6. Analysis of Phenix End-of-Life asymmetry test with multi-dimensional pool modeling of MARS-LMR code

    International Nuclear Information System (INIS)

    Jeong, H.-Y.; Ha, K.-S.; Choi, C.-W.; Park, M.-G.

    2015-01-01

    Highlights: • Pool behaviors under asymmetrical condition in an SFR were evaluated with MARS-LMR. • The Phenix asymmetry test was analyzed one-dimensionally and multi-dimensionally. • One-dimensional modeling has limitation to predict the cold pool temperature. • Multi-dimensional modeling shows improved prediction of stratification and mixing. - Abstract: The understanding of complicated pool behaviors and its modeling is essential for the design and safety analysis of a pool-type Sodium-cooled Fast Reactor. One of the remarkable recent efforts on the study of pool thermal–hydraulic behaviors is the asymmetrical test performed as a part of Phenix End-of-Life tests by the CEA. To evaluate the performance of MARS-LMR code, which is a key system analysis tool for the design of an SFR in Korea, in the prediction of thermal hydraulic behaviors during an asymmetrical condition, the Phenix asymmetry test is analyzed with MARS-LMR in the present study. Pool regions are modeled with two different approaches, one-dimensional modeling and multi-dimensional one, and the prediction results are analyzed to identify the appropriateness of each modeling method. The prediction with one-dimensional pool modeling shows a large deviation from the measured data at the early stage of the test, which suggests limitations to describe the complicated thermal–hydraulic phenomena. When the pool regions are modeled multi-dimensionally, the prediction gives improved results quite a bit. This improvement is explained by the enhanced modeling of pool mixing with the multi-dimensional modeling. On the basis of the results from the present study, it is concluded that an accurate modeling of pool thermal–hydraulics is a prerequisite for the evaluation of design performance and safety margin quantification in the future SFR developments

  7. Analysis of Phenix end-of-life natural convection test with the MARS-LMR code

    International Nuclear Information System (INIS)

    Jeong, H. Y.; Ha, K. S.; Lee, K. L.; Chang, W. P.; Kim, Y. I.

    2012-01-01

    The end-of-life test of Phenix reactor performed by the CEA provided an opportunity to have reliable and valuable test data for the validation and verification of a SFR system analysis code. KAERI joined this international program for the analysis of Phenix end-of-life natural circulation test coordinated by the IAEA from 2008. The main objectives of this study were to evaluate the capability of existing SFR system analysis code MARS-LMR and to identify any limitation of the code. The analysis was performed in three stages: pre-test analysis, blind posttest analysis, and final post-test analysis. In the pre-test analysis, the design conditions provided by the CEA were used to obtain a prediction of the test. The blind post-test analysis was based on the test conditions measured during the tests but the test results were not provided from the CEA. The final post-test analysis was performed to predict the test results as accurate as possible by improving the previous modeling of the test. Based on the pre-test analysis and blind test analysis, the modeling for heat structures in the hot pool and cold pool, steel structures in the core, heat loss from roof and vessel, and the flow path at core outlet were reinforced in the final analysis. The results of the final post-test analysis could be characterized into three different phases. In the early phase, the MARS-LMR simulated the heat-up process correctly due to the enhanced heat structure modeling. In the mid phase before the opening of SG casing, the code reproduced the decrease of core outlet temperature successfully. Finally, in the later phase the increase of heat removal by the opening of the SG opening was well predicted with the MARS-LMR code. (authors)

  8. Simulation of the core flowering End-of-life test realized on Phenix reactor

    International Nuclear Information System (INIS)

    Prulhiere, G.; Fontaine, B.; Frosio, T.

    2013-01-01

    After the definitive shutdown of the Phenix sodium cooled fast reactor and before its decommissioning, a final set of tests were performed covering core physics, fuel behavior and thermal hydraulics areas. In addition, the program included two tests related to the comprehension of the four negative reactivity transients experienced during the reactor operation in 1989 and 1990. One of these tests, called 'core flowering test' focused on the relation between sub-assemblies mechanical displacements and reactivity variations. This test was carried out by introducing a mechanical device pushing on the six fuel assemblies neighbors. This device was located at two different core positions: at the center and at a peripheral one. The reactivity effect induced by core flowering was measured at different temperatures in the range of 180 to 350 Celsius degrees. The simulation of such a test requires the use of a neutronic computing code which is not compelled to the definition of regular geometrical lattices. Moreover, a system permitting an easy and change-allowing way to define geometries and deformations is needed. That is why the use of a Monte Carlo code like TRIPOLI coupled to ROOT system was chosen to simulate this test. The displacement of each sub-assembly was estimated upstream of this study using the static mechanics code HARMONIE. To perform this calculations with a satisfying precision, several hundreds millions of neutrons particles were needed for the modelling. (author)

  9. Modeling of Phenix End-of-Life control rod withdrawal benchmark with DYN3D SFR version

    Energy Technology Data Exchange (ETDEWEB)

    Nikitin, Evgeny; Fridman, Emil [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Reactor Safety

    2017-06-01

    The reactor dynamics code DYN3D is currently under extension for Sodium cooled Fast Reactor applications. The control rod withdrawal benchmark from the Phenix End-of-Life experiments was selected for verification and validation purposes. This report presents some selected results to demonstrate the feasibility of using DYN3D for steady-state Sodium cooled Fast Reactor analyses.

  10. MARS-LMR modeling for the post-test analysis of Phenix End-of-Life natural circulation

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Chang, Won Pyo; Lee, Kwi Lim

    2011-01-01

    For a successful design and analysis of Sodium cooled Fast Reactor (SFR), it is required to have a reliable and well-proven system analysis code. To achieve this purpose, KAERI is enhancing the modeling capability of MARS code by adding the SFR-specific models such as pressure drop model, heat transfer model and reactivity feedback model. This version of MARS-LMR will be used as a basic tool in the design and analysis of future SFR systems in Korea. Before wide application of MARS-LMR code, it is required to verify and validate the code models through analyses for appropriate experimental data or analytical results. The end-of-life test of Phenix reactor performed by the CEA provided a unique opportunity to have reliable test data which is very valuable in the validation and verification of a SFR system analysis code. The KAERI joined this international program of the analysis of Phenix end-of-life natural circulation test coordinated by the IAEA from 2008. The main test of natural circulation was completed in 2009. Before the test the KAERI performed the pre-test analysis based on the design condition provided by the CEA. Then, the blind post-test analysis was also performed based on the test conditions measured during the test before the CEA provide the final test results. Finally, the final post-test analysis was performed recently to predict the test results as accurate as possible. This paper introduces the modeling approach of the MARS-LMR used in the final post-test analysis and summarizes the major results of the analysis

  11. Blind post-test analysis of Phenix End-of-Life natural circulation test with the MARS-LMR

    International Nuclear Information System (INIS)

    Jeong, Hae Yong; Ha, Kwi Seok; Kwon, Young Min; Chang, Won Pyo; Suk, Su Dong; Lee, Kwi Lim

    2010-01-01

    KAERI is developing a system analysis code, MARS-LMR, for the application to a sodium-cooled fast reactor (SFR). This code will be used as a basic tool in the design and analysis of future SFR systems in Korea. Before wide application of a system analysis code, it is required to verify and validate the code models through analyses for appropriate experimental data or analytical results. The MARS-LMR code has been developed from MARS code which had been well verified and validated for a pressurized water reactor (PWR) system. The MARS-LMR code shares the same form of governing equations and solution schemes with MARS code, which eliminates the need of independent verification procedure. However, it is required to validate the applicability of the code to an SFR system because it adopts some dedicated heat transfer models, pressure drop models, and material properties models for a sodium system. Phenix is a medium-sized pool-type SFR successfully operated for 35 years since 1973. This reactor reached its final shutdown in February 2009. An international program of Phenix end-of-life (EOL) test was followed and some valuable information was obtained from the test, which will be useful for the validation of SFR system analysis code. In the present study, the performance of MARS-LMR code is evaluated through a blind calculation with the boundary conditions measured in the real test. The post-test analysis results are also compared with the test data generated in the test

  12. Coupled thermal-hydraulic and neutronic simulations of Phenix control rod withdrawal tests with SIMMER-IV

    International Nuclear Information System (INIS)

    Kriventsev, Vladimir; Gabrielli, Fabrizio; Rineiski, Andrei

    2014-01-01

    The “end-of-life” tests performed in the Phenix reactor before its final shutdown in 2009, in particular the Control Rod (CR) withdrawal experiments provide an excellent opportunity for the validation and verification of the reactor physics computer codes and modeling approaches. SIMMER-IV, a modern three-dimensional reactor safety code, has been recently employed at Karlsruhe Institute of Technology (KIT) for simulating Phenix experiments in the framework of a benchmark exercise organized under the IAEA project. In this paper, we report and discuss main results obtained with SIMMER-IV at KIT. Particular attention is devoted to the coupling features of thermal-hydraulics and neutronics and their mutual influences. The reactor reactivity, power and neutron flux distributions calculated with SIMMER-IV are in good agreement both with experimental results and with calculations with advanced neutronics codes, such as ERANOS, while the CR reactivity worth is overestimated due to neglecting heterogeneity effects. Because of its multi-physics capabilities SIMMER also calculates the temperature distributions which are in a good agreement with the experimental test results. In this work we describe the improvements in SIMMER neutronics model by employing a correction that is based on the results of cell calculations performed with ERANOS. The study confirms that the 3D SIMMER-IV code can accurately predict major fast reactor neutronics and thermal hydraulic parameters, provided that a special treatment is employed for CR modeling. The results of calculations are analyzed in frames of SIMMER-IV validation and verification assessment. (author)

  13. Benchmark Analyses on the Natural Circulation Test Performed During the PHENIX End-of-Life Experiments. Final Report of a Co-ordinated Research Project 2008-2011

    International Nuclear Information System (INIS)

    2013-07-01

    The International Atomic Energy Agency (IAEA) supports Member State activities in the area of advanced fast reactor technology development by providing a forum for information exchange and collaborative research programmes. The Agency's activities in this field are mainly carried out within the framework of the Technical Working Group on Fast Reactors (TWG-FR), which assists in the implementation of corresponding IAEA activities and ensures that all technical activities are in line with the expressed needs of Member States. Among its broad range of activities, the IAEA proposes and establishes coordinated research projects (CRPs) aimed at the improvement of Member State capabilities in the area of fast reactor design and analysis. An important opportunity to undertake collaborative research was provided by the experimental campaign of the French Alternative Energies and Atomic Energy Commission (CEA) in the prototype sodium fast reactor PHENIX before it was shut down in 2009. The overall purpose of the end of life tests was to gather additional experience on the operation of sodium cooled reactors. As the CEA opened the experiments to international cooperation, in 2007 the IAEA launched a CRP on ''Control Rod Withdrawal and Sodium Natural Circulation Tests Performed during the PHENIX End-of-Life Experiments''. The CRP, with the participation of institutes from eight countries, contributed to improving capabilities in sodium cooled reactor simulation through code verification and validation, with particular emphasis on temperature and power distribution calculations and the analysis of sodium natural circulation phenomena. The objective of this report is to document the results and main achievements of the benchmark analyses on the natural circulation test performed in the framework of the PHENIX end of life experimental campaign

  14. End of Life Issues

    Science.gov (United States)

    Planning for the end of life can be difficult. But by deciding what end-of-life care best suits your needs when you are healthy, you can ... right choices when the time comes. End-of-life planning usually includes making choices about the following: ...

  15. End of Life Care

    Science.gov (United States)

    ... Related Topics Choosing Wisely Join our e-newsletter! Aging & Health A to Z End of Life Care ... be used. Ice chips, popsicles, moist swabs, or artificial saliva can help prevent the mouth from becoming ...

  16. End of Life: Suicide Grief

    Science.gov (United States)

    Healthy Lifestyle End of life A loved one's suicide can be emotionally devastating. Use healthy coping strategies — ... Clinic Staff When a loved one dies by suicide, overwhelming emotions can leave you reeling. Your grief ...

  17. Steam generator thermal-hydraulics

    International Nuclear Information System (INIS)

    Inch, W.W.; Scott, D.A.; Carver, M.B.

    1980-01-01

    This paper discusses a code for detailed numerical modelling of steam generator thermal-hydraulics, and describes related experimental programs designed to promote in-depth understanding of three-dimensional two-phase flow. (auth)

  18. End of Life: An Overview

    Science.gov (United States)

    Toner, Mary Ann; Shadden, Barbara B.

    2012-01-01

    Speech-language pathologists (SLPs) provide services to patients confronting the end of life (EOL) in a variety of settings. Instead of targeting improvement of health or sustaining life, EOL services focus primarily on quality of life. Although SLPs may not consider themselves core members of the health care team providing EOL services, the…

  19. GCFR thermal-hydraulic experiments

    International Nuclear Information System (INIS)

    Schlueter, G.; Baxi, C.B.; Dalle Donne, M.; Gat, U.; Fenech, H.; Hanson, D.; Hudina, M.

    1980-01-01

    The thermal-hydraulic experimental studies performed and planned for the Gas-Cooled Fast Reactor (GCFR) core assemblies are described. The experiments consist of basic studies performed to obtain correlations, and bundle experiments which provide input for code validation and design verification. These studies have been performed and are planned at European laboratories, US national laboratories, Universities in the US, and at General Atomic Company

  20. PHENIX REPORTS

    International Nuclear Information System (INIS)

    Thompson, Timothy C.

    1998-01-01

    This report contains individual progress reports for the months of December 1997 through May 1998 on the Phenix program at Hytec. Topics include the Phenix muon detector chamber flow analysis; the Phenix Muon detector deformation and motion/tolerance study of Stations 1, 2, and 3; finite element mount/electron shield structural analysis; South Station 3 muon detector deformation analysis; and Station 1 muon detector panel assembly and fabrication sequences

  1. PHENIX REPORTS

    Energy Technology Data Exchange (ETDEWEB)

    TIMOTHY C. THOMPSON - HYTEC, INC.

    1998-12-10

    This report contains individual progress reports for the months of December 1997 through May 1998 on the Phenix program at Hytec. Topics include the Phenix muon detector chamber flow analysis; the Phenix Muon detector deformation and motion/tolerance study of Stations 1, 2, and 3; finite element mount/electron shield structural analysis; South Station 3 muon detector deformation analysis; and Station 1 muon detector panel assembly and fabrication sequences.

  2. A HISTORICAL PERSPECTIVE OF NUCLEAR THERMAL HYDRAULICS

    Energy Technology Data Exchange (ETDEWEB)

    D’Auria, F; Rohatgi, Upendra S.

    2017-01-12

    The nuclear thermal-hydraulics discipline was developed following the needs for nuclear power plants (NPPs) and, to a more limited extent, research reactors (RR) design and safety. As in all other fields where analytical methods are involved, nuclear thermal-hydraulics took benefit of the development of computers. Thermodynamics, rather than fluid dynamics, is at the basis of the development of nuclear thermal-hydraulics together with the experiments in complex two-phase situations, namely, geometry, high thermal density, and pressure.

  3. Reactor Thermal Hydraulic Numerical Calculation And Modeling

    International Nuclear Information System (INIS)

    Duong Ngoc Hai; Dang The Ba

    2008-01-01

    In the paper the results of analysis of thermal hydraulic state models using the numerical codes such as COOLOD, EUREKA and RELAP5 for simulation of the reactor thermal hydraulic states are presented. The calculations, analyses of reactor thermal hydraulic state and safety were implemented using different codes. The received numerical results, which were compared each to other, to experiment measurement of Dalat (Vietnam) research reactor and published results, show their appropriateness and capacity for analyses of different appropriate cases. (author)

  4. Overview of the system alone and system/CFD coupled calculations of the PHENIX Natural Circulation Test within the THINS project

    Energy Technology Data Exchange (ETDEWEB)

    Pialla, David, E-mail: david.pialla@cea.fr [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), DEN/DM2S/STMF, 17 rue des martyrs, 38054 Grenoble Cedex 9 (France); Tenchine, Denis [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), DEN/DM2S/STMF, 17 rue des martyrs, 38054 Grenoble Cedex 9 (France); Li, Simon [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), DEN/DM2S/STMF, 91191 Gif-sur-Yvette Cedex (France); Gauthe, Paul; Vasile, Alfredo [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), DEN/DER/SESI, 13108 Saint Paul Lez Durance Cedex (France); Baviere, Roland; Tauveron, Nicolas; Perdu, Fabien [Commissariat à l’Energie Atomique et aux Energies Alternatives (CEA), DEN/DM2S/STMF, 17 rue des martyrs, 38054 Grenoble Cedex 9 (France); Maas, Ludovic; Cocheme, François [Institut de Radioprotection et de Sûreté Nucléaire (IRSN), PSN/SEMIA/BAST, B.P. 17, 92262 Fontenay-aux-Roses Cedex (France); Huber, Klaus; Cheng, Xu [Karlsruhe Institute of Technology (KIT), Institute of Fusion and Reactor Technology (IFRT), Kaiserstraße 12, Building 07.08, 76131 Karlsruhe (Germany)

    2015-08-15

    Highlights: • The PHENIX natural convection test performed during the end of life tests program. • The calculation with system codes and theirs limits. • The calculation with coupling CFD and system code, which allows better prediction. • The tasks of code validation have been done in the frame of the THINS project. - Abstract: The PHENIX sodium cooled fast reactor started operation in 1973 and was shut down in 2009. Before decommissioning, an ultimate test program was designed and performed to provide valuable data for the development of future sodium cooled fast reactors, as the so-called Astrid prototype in France. Among these ultimate tests, a thermal-hydraulic Natural Convection Test (NCT) was set-up in June 2009. Starting from a reduced power state of 120 MWt, the NCT consists of a loss of the heat sink combined with a reactor scram and a primary pumps trip leading to stabilized natural circulation in the primary sodium system. The thermal-hydraulics innovative system project (THINS project), sponsored by the European Community in the frame of the 7th FP has selected this transient for validation of both stand-alone system code simulations and coupled simulations using system and CFD codes. Participants from three organizations (CEA, IRSN and KIT) have addressed this transient using different system codes (CATHARE, DYN2B and ATHLET) and CFD codes (TRIO-U and OPEN FOAM). The present paper depicts the different modeling approaches, methodologies and compares the numerical results with the available experimental data. Finally, the main lessons learned from the work performed within the THINS project on the PHENIX NCT with respect to code development and validation are summarized.

  5. HANARO thermal hydraulic accident analysis

    Energy Technology Data Exchange (ETDEWEB)

    Park, Chul; Kim, Heon Il; Lee, Bo Yook; Lee, Sang Yong [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-06-01

    For the safety assessment of HANARO, accident analyses for the anticipated operational transients, accident scenarios and limiting accident scenarios were conducted. To do this, the commercial nuclear reactor system code. RELAP5/MOD2 was modified to RELAP5/KMRR; the thermal hydraulic correlations and the heat exchanger model was changed to incorporate HANARO characteristics. This report summarizes the RELAP/KMRR calculation results and the subchannel analyses results based on the RELAP/KMRR results. During the calculation, major concern was placed on the integrity of the fuel. For all the scenarios, the important accident analysis parameters, i.e., fuel centerline temperatures and the minimum critical heat flux ratio(MCHFR), satisfied safe design limits. It was verified, therefore, that the HANARO was safely designed. 21 tabs., 89 figs., 39 refs. (Author) .new.

  6. Challenges in end-of-life communication.

    Science.gov (United States)

    Galushko, Maren; Romotzky, Vanessa; Voltz, Raymond

    2012-09-01

    The purpose of this review is to give an overview of challenges that have been addressed in recent research in end-of-life communication. Diversity of difficulties that may occur in communication about end-of-life issues has been showed. The emotional quality of this communication requires special skills from professionals involved. Studies showed that physicians and medical students are often overstrained and avoid end-of-life discussions. Health professionals and patients are often ambivalent about end-of-life discussions. Nevertheless, professionals are expected to initiate these in an honest, needs-oriented way. Patient preferences are difficult to infer and have to be assessed explicitly and regularly. Studies showed that the emotional impact of end-of-life discussions can lead to a high burden or avoidance of professionals. Interdisciplinary, multi-professional work can support health professionals in end-of-life care but often structural barriers obstruct possible benefits. Health professionals need to initiate end-of-life communication in a sensitive way. Specific demands for health professionals in end-of-life communication are to differentiate own emotions and life events from those of patients and to deal with both adequately. Moreover, structural aspects can lead to difficulties between different specialties, professions and sectors, which can have a negative impact on adequate care for patient and relatives. Special efforts for improvement are needed.

  7. Liquid metal thermal-hydraulics

    International Nuclear Information System (INIS)

    Kottowski-Duemenil, H.M.

    1994-01-01

    This textbook is a report of the 26 years activity of the Liquid Metal Boiling Working Group (LMBWG). It summarizes the state of the art of liquid metal thermo-hydraulics achieved through the collaboration of scientists concerned with the development of the Fast Breeder Reactor. The first chapter entitled ''Liquid Metal Boiling Behaviour'', presents the background and boiling mechanisms. This section gives the reader a brief but thorough survey on the superheat phenomena in liquid metals. The second chapter of the text, ''A Review of Single and Two-Phase Flow Pressure Drop Studies and Application to Flow Stability Analysis of Boiling Liquid Metal Systems'' summarizes the difficulty of pressure drop simulation of boiling sodium in core bundles. The third chapter ''Liquid Metal Dry-Out Data for Flow in Tubes and Bundles'' describes the conditions of critical heat flux which limits the coolability of the reactor core. The fourth chapter dealing with the LMFBR specific topic of ''Natural Convection Cooling of Liquid Metal Systems''. This chapter gives a review of both plant experiments and out-of-pile experiments and shows the advances in the development of computing power over the past decade of mathematical modelling ''Subassembly Blockages Suties'' are discussed in chapter five. Chapter six is entitled ''A Review of the Methods and Codes Available for the Calculation on Thermal-Hydraulics in Rod-Cluster and other Geometries, Steady state and Transient Boiling Flow Regimes, and the Validation achieves''. Codes available for the calculation of thermal-hydraulics in rod-clusters and other geometries are reviewed. Chapter seven, ''Comparative Studies of Thermohydraulic Computer Code Simulations of Sodium Boiling under Loss of Flow Conditions'', represents one of the key activities of the LMBWG. Several benchmark exercises were performed with the aim of transient sodium boiling simulation in single channels and bundle blockages under steady state conditions and loss of

  8. Thermal-hydraulic unreliability of passive systems

    International Nuclear Information System (INIS)

    Tzanos, C.P.; Saltos, N.T.

    1995-01-01

    Advanced light water reactor designs like AP600 and the simplified boiling water reactor (SBWR) use passive safety systems for accident prevention and mitigation. Because these systems rely on natural forces for their operation, their unavailability due to hardware failures and human error is significantly smaller than that of active systems. However, the coolant flows predicted to be delivered by these systems can be subject to significant uncertainties, which in turn can lead to a significant uncertainty in the predicted thermal-hydraulic performance of the plant under accident conditions. Because of these uncertainties, there is a probability that an accident sequence for which a best estimate thermal-hydraulic analysis predicts no core damage (success sequence) may actually lead to core damage. For brevity, this probability will be called thermal-hydraulic unreliability. The assessment of this unreliability for all the success sequences requires very expensive computations. Moreover, the computational cost increases drastically as the required thermal-hydraulic reliability increases. The required computational effort can be greatly reduced if a bounding approach can be used that either eliminates the need to compute thermal-hydraulic unreliabilities, or it leads to the analysis of a few bounding sequences for which the required thermal-hydraulic reliability is relatively small. The objective of this paper is to present such an approach and determine the order of magnitude of the thermal-hydraulic unreliabilities that may have to be computed

  9. Experimental thermal hydraulics in support of FBR

    International Nuclear Information System (INIS)

    Padmakumar, G.; Anand Babu, C.; Kalyanasundaram, P.; Vaidyanathan, G.

    2009-01-01

    The thermal hydraulic design plays a crucial role for the safe and economical deployment of Liquid Metal Cooled Fast Breeder Reactor (LMFBR). Robust experimental programmes are required in support of LMFBR thermal hydraulics design. The philosophy of testing has been to construct small scale models to understand the physical behaviour and to build larger scale models to optimize the component design. The experiments are conducted either in sodium or using a simulant like water/air. The paper gives a brief account of the various thermal hydraulic experiments carried out in support of the design of Prototype Fast Breeder Reactor (PFBR). (author)

  10. Pharmacotherapy at the end-of-life.

    LENUS (Irish Health Repository)

    O'Mahony, Denis

    2011-07-01

    Older people reaching end-of-life status are particularly at risk from inter-related adverse effects of pharmacotherapy, including polypharmacy, inappropriate medications and adverse drug events. These adverse effects of pharmacotherapy may be highly detrimental, as well as highly expensive. End-of-life pharmacotherapy is sometimes perceived to be complex and challenging, probably unnecessarily. This relates in part to the poorly developed evidence base and lack of high-quality research in this area. In this article, we deal with some of the key issues relating to pharmacotherapy in end-of-life patients, namely (i) the guiding principles of drug selection, (ii) the main drugs and drug classes that are best avoided, (iii) the benefits of \\'oligopharmacy\\' (i.e. deliberate avoidance of polypharmacy) in end-of-life patients.

  11. TRACE analysis of Phenix core response to an increase of the core inlet sodium temperature

    Energy Technology Data Exchange (ETDEWEB)

    Chenu, A., E-mail: aurelia.chenu@psi.ch [Paul Scherrer Inst., Villigen PSI (Switzerland); Ecole Polytechnique Federale (Switzerland); Mikityuk, K., E-mail: konstantin.mikityuk@psi.ch [Paul Scherrer Inst., Villigen PSI (Switzerland); Adams, R., E-mail: robert.adams@psi.ch [Paul Scherrer Inst., Villigen PSI (Switzerland); Eidgenossische Technische Hochschule, Zurich (Switzerland); Chawla, R., E-mail: rakesh.chawla@epfl.ch [Paul Scherrer Inst., Villigen PSI (Switzerland); Ecole Polytechnique Federale (Switzerland)

    2011-07-01

    This work presents the analysis, using the TRACE code, of the Phenix core response to an inlet sodium temperature increase. The considered experiment was performed in the frame of the Phenix End-Of-Life (EOL) test program of the CEA, prior to the final shutdown of the reactor. It corresponds to a transient following a 40°C increase of the core inlet temperature, which leads to a power decrease of 60%. This work focuses on the first phase of the transient, prior to the reactor scram and pump trip. First, the thermal-hydraulic TRACE model of the core developed for the present analysis is described. The kinetic parameters and feedback coefficients for the point kinetic model were first derived from a 3D static neutronic ERANOS model developed in a former study. The calculated kinetic parameters were then optimized, before use, on the basis of the experimental reactivity in order to minimize the error on the power calculation. The different reactivity feedbacks taken into account include various expansion mechanisms that have been specifically implemented in TRACE for analysis of fast-neutron spectrum systems. The point kinetic model has been used to study the sensitivity of the core response to the different feedback effects. The comparison of the calculated results with the experimental data reveals the need to accurately calculate the reactivity feedback coefficients. This is because the reactor response is very sensitive to small reactivity changes. This study has enabled us to study the sensitivity of the power change to the different reactivity feedbacks and define the most important parameters. As such, it furthers the validation of the FAST code system, which is being used to gain a more in-depth understanding of SFR core behavior during accidental transients. (author)

  12. Horizontal steam generator thermal-hydraulics

    Energy Technology Data Exchange (ETDEWEB)

    Ubra, O. [SKODA Praha Company, Prague (Czechoslovakia); Doubek, M. [Czech Technical Univ., Prague (Czechoslovakia)

    1995-09-01

    Horizontal steam generators are typical components of nuclear power plants with pressure water reactor type VVER. Thermal-hydraulic behavior of horizontal steam generators is very different from the vertical U-tube steam generator, which has been extensively studied for several years. To contribute to the understanding of the horizontal steam generator thermal-hydraulics a computer program for 3-D steady state analysis of the PGV-1000 steam generator has been developed. By means of this computer program, a detailed thermal-hydraulic and thermodynamic study of the horizontal steam generator PGV-1000 has been carried out and a set of important steam generator characteristics has been obtained. The 3-D distribution of the void fraction and 3-D level profile as functions of load and secondary side pressure have been investigated and secondary side volumes and masses as functions of load and pressure have been evaluated. Some of the interesting results of calculations are presented in the paper.

  13. End-of-life decisions: Christian perspectives.

    Science.gov (United States)

    Stempsey, William E

    1997-12-01

    While legal rights to make medical treatment decisions at the end of one's life have been recognized by the courts, particular religious traditions put axiological and metaphysical meat on the bare bones of legal rights. Mere legal rights do not capture the full reality, meaning and importance of death. End-of-life decisions reflect not only the meaning we find in dying, but also the meaning we have found in living. The Christian religions bring particular understandings of the vision of life as a gift from God, human responsibility for stewardship of that life, the wholeness of the person, and the importance of the dying process in preparing spiritually for life beyond earthly life, to bear on end-of-life decisions.

  14. [End-of-life care and end-of-life medical decisions: the ITAELD study].

    Science.gov (United States)

    Miccinesi, Guido; Puliti, Donella; Paci, Eugenio

    2011-01-01

    To describe the attitudes towards end of life care and the practice of end-of-life medical decisions with possible life-shortening effect among Italian physicians. Cross sectional study (last death among the assisted patients in the last 12 months was considered). In the year 2007, 5,710 GPs and 8,950 hospital physicians were invited all over Italy to participate in the ITAELDstudy through anonymous mail questionnaire. Proportion of agreement with statements on end-of-life care issues. Proportion of deaths with an end-of-life medical decision. The response rate was 19.2%. The 65% of respondents agreed with the duty to respect any non-treatment request of the competent patient, the 55% agreed with the same duty in case of advanced directives, the 39% in case of proxy's request. The 53% of respondents agreed with the ethical acceptability of active euthanasia in selected cases. Among 1,850 deaths the 57.7% did not receive any end-of-life medical decision. For a further 21.0% no decision was possible, being sudden and unexpected deaths. In the remaining 21.3% at least one end-of-life medical decision was reported: 0.8% was classified as physician assisted death, 20.5% as non-treatment decision. Among all deceased the 19.6% were reported to have been deeply sedated. Being favourable to the use of opioids in terminal patients was associated to non-treatment decisions with possible but non-intentional life shortening effect; agreeing with the duty to fully respect any actual non-treatment request of the competent patient was associated to end-of life medical decisions with intentional life-shortening effect (adjusted OR>10 in both cases). The life stance and ethical beliefs of physicians determine their behaviour at the end of life wherever specific statements of law are lacking. Therefore education and debate are needed on these issues.

  15. Proceedings of the third nuclear thermal hydraulics meeting

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    This book contains the proceedings of the Thermal Hydraulics Division of the American Nuclear Society. The papers presented include: Simulator qualification using engineering codes and Development of thermal hydraulic analysis capabilities for Oyster Creek

  16. Contribution to the study of thermal-hydraulic problems in nuclear reactors

    International Nuclear Information System (INIS)

    Cognet, G.

    1998-01-01

    In nuclear reactors, whatever the type considered, Pressurized Water Water Reactors (PWRs), Fast Breeder reactors (FBRs)..., thermal-hydraulics, the science of fluid mechanics and thermal behaviour, plays an essential role, both in nominal operating and accidental conditions. Fluid can either be the primary fluid (liquid or gas) or a very specific fluid called corium, which, in case of severe accident, could result from core and environning structure melting. The work reported here represents a 20-year contribution to thermal-hydraulic issues which could occur in FBRs and PWRs. Working on these two types of reactors, both in nominal and severe accident situations, has allowed me to compare the problems and to realize the importance of communication between research teams. The evolution in the complexity of studied problems, unavoidable in order to reduce costs and significantly improve safety, has led me from numerical modelling of single-phase flow turbulence to high temperature real melt experiments. The difficulties encountered in understanding the observed phenomena and in increasing experimental databases for computer code qualification have often entailed my participation in specific measurement device developments or adaptations, in particular non-intrusive devices generally based on optical techniques. Being concerned about the end-use of this research work, I actively participated in 'in-situ' thermalhydraulic experiments in the FBRs: Phenix and Super-Phenix, of which I appreciated their undeniable scientific contribution. In my opinion, the thermal-hydraulic questions related to severe accidents are the most complex as they are at the cross-roads of several scientific specialities. Consequently, they require a multi-disciplinary approach and a continuous see-saw motion between experimentalists and modelling teams. After a brief description of the various problems encountered, the main ones are reported. Finally, the importance for research teams to

  17. Analysis of uncertainties of thermal hydraulic calculations

    International Nuclear Information System (INIS)

    Macek, J.; Vavrin, J.

    2002-12-01

    In 1993-1997 it was proposed, within OECD projects, that a common program should be set up for uncertainty analysis by a probabilistic method based on a non-parametric statistical approach for system computer codes such as RELAP, ATHLET and CATHARE and that a method should be developed for statistical analysis of experimental databases for the preparation of the input deck and statistical analysis of the output calculation results. Software for such statistical analyses would then have to be processed as individual tools independent of the computer codes used for the thermal hydraulic analysis and programs for uncertainty analysis. In this context, a method for estimation of a thermal hydraulic calculation is outlined and selected methods of statistical analysis of uncertainties are described, including methods for prediction accuracy assessment based on the discrete Fourier transformation principle. (author)

  18. Thermal hydraulics in undergraduate nuclear engineering education

    International Nuclear Information System (INIS)

    Theofanous, T.G.

    1986-01-01

    The intense safety-related research efforts of the seventies in reactor thermal hydraulics have brought about the recognition of the subject as one of the cornerstones of nuclear engineering. Many nuclear engineering departments responded by building up research programs in this area, and mostly as a consequence, educational programs, too. Whether thermal hydraulics has fully permeated the conscience of nuclear engineering, however, remains yet to be seen. The lean years that lie immediately ahead will provide the test. The purpose of this presentation is to discuss the author's own educational activity in undergraduate nuclear engineering education over the past 10 yr or so. All this activity took place at Purdue's School of Nuclear Engineering. He was well satisfied with the results and expects to implement something similar at the University of California in Santa Barbara in the near future

  19. Thermal-hydraulic analysis of nuclear reactors

    CERN Document Server

    Zohuri, Bahman

    2015-01-01

    This text covers the fundamentals of thermodynamics required to understand electrical power generation systems and the application of these principles to nuclear reactor power plant systems. It is not a traditional general thermodynamics text, per se, but a practical thermodynamics volume intended to explain the fundamentals and apply them to the challenges facing actual nuclear power plants systems, where thermal hydraulics comes to play.  Written in a lucid, straight-forward style while retaining scientific rigor, the content is accessible to upper division undergraduate students and aimed at practicing engineers in nuclear power facilities and engineering scientists and technicians in industry, academic research groups, and national laboratories. The book is also a valuable resource for students and faculty in various engineering programs concerned with nuclear reactors. This book also: Provides extensive coverage of thermal hydraulics with thermodynamics in nuclear reactors, beginning with fundamental ...

  20. Virginia Power thermal-hydraulics methods

    International Nuclear Information System (INIS)

    Anderson, R.C.; Basehore, K.L.; Harrell, J.R.

    1987-01-01

    Virginia Power's nuclear safety analysis group is responsible for the safety analysis of reload cores for the Surry and North Anna power stations, including the area of core thermal-hydraulics. Postulated accidents are evaluated for potential departure from nucleate boiling violations. In support of these tasks, Virginia Power has employed the COBRA code and the W-3 and WRB-1 DNB correlations. A statistical DNBR methodology has also been developed. The code, correlations and statistical methodology are discussed

  1. Thermal-Hydraulic Experiment Facility (THEF)

    International Nuclear Information System (INIS)

    Martinell, J.S.

    1982-01-01

    This paper provides an overview of the Thermal-Hydraulic Experiment Facility (THEF) at the Idaho National Engineering Laboratory (INEL). The overview describes the major test systems, measurements, and data acquisition system, and presents objectives, facility configuration, and results for major experimental projects recently conducted at the THEF. Plans for future projects are also discussed. The THEF is located in the Water Reactor Research Test Facility (WRRTF) area at the INEL

  2. Thermal hydraulics and mechanics core design programs

    International Nuclear Information System (INIS)

    Heinecke, J.

    1992-10-01

    The report documents the work performed within the Research and Development Task T hermal hydraulics and mechanics core design programs , funded by the German government. It contains the development of new codes, the extension of existing codes, the qualification and verification of codes and the development of a code library. The overall goal of this work was to adapt the system of thermal hydraulics and mechanics codes to the permanently growing requirements of the status of science and technology

  3. Thermal-hydraulics of actinide burner reactors

    International Nuclear Information System (INIS)

    Takizuka, Takakazu; Mukaiyama, Takehiko; Takano, Hideki; Ogawa, Toru; Osakabe, Masahiro.

    1989-07-01

    As a part of conceptual study of actinide burner reactors, core thermal-hydraulic analyses were conducted for two types of reactor concepts, namely (1) sodium-cooled actinide alloy fuel reactor, and (2) helium-cooled particle-bed reactor, to examine the feasibility of high power-density cores for efficient transmutation of actinides within the maximum allowable temperature limits of fuel and cladding. In addition, calculations were made on cooling of actinide fuel assembly. (author)

  4. Pricing end-of-life components

    Science.gov (United States)

    Vadde, Srikanth; Kamarthi, Sagar V.; Gupta, Surendra M.

    2005-11-01

    The main objective of a product recovery facility (PRF) is to disassemble end-of-life (EOL) products and sell the reclaimed components for reuse and recovered materials in second-hand markets. Variability in the inflow of EOL products and fluctuation in demand for reusable components contribute to the volatility in inventory levels. To stay profitable the PRFs ought to manage their inventory by regulating the price appropriately to minimize holding costs. This work presents two deterministic pricing models for a PRF bounded by environmental regulations. In the first model, the demand is price dependent and in the second, the demand is both price and time dependent. The models are valid for single component with no inventory replenishment sale during the selling horizon . Numerical examples are presented to illustrate the models.

  5. Networking to improve end of life care

    Science.gov (United States)

    2009-01-01

    Network organisations are increasingly common in healthcare. This paper describes an example of clinically led networking, which improved end of life care (EOLC) in care homes, differentiating between a ‘network’ as a formal entity and the more informal process of ‘networking’. The paper begins with a brief discussion of networks and their development in healthcare, then an overview of EOLC policy, the case setting and methods. The paper describes four key features of this networking; (1) how it enabled discussions and implemented processes to help people address difficult taboos about dying; (2) how personal communication and ‘distributed leadership’ facilitated learning; (3) how EOLC occasionally lapsed during the handover of patient care, where personal relationship and communication were weaker; and (4) how successful learning and sharing of best practice was fragile and could be potentially undermined by wider financial pressures in the NHS. PMID:25949588

  6. PHENIX for Beginners

    Science.gov (United States)

    Zajc, W. A.; Fachini, P.

    2002-10-01

    An introduction to the PHENIX detector and to the PHENIX physics program is presented. The PHENIX physics results presented here are those from the the first RHIC (Relativistic Heavy Ion Collider) run with Au+Au collisions at RADICAL:[[RADICAND:[SNN

  7. Review of computational thermal-hydraulic modeling

    International Nuclear Information System (INIS)

    Keefer, R.H.; Keeton, L.W.

    1995-01-01

    Corrosion of heat transfer tubing in nuclear steam generators has been a persistent problem in the power generation industry, assuming many different forms over the years depending on chemistry and operating conditions. Whatever the corrosion mechanism, a fundamental understanding of the process is essential to establish effective management strategies. To gain this fundamental understanding requires an integrated investigative approach that merges technology from many diverse scientific disciplines. An important aspect of an integrated approach is characterization of the corrosive environment at high temperature. This begins with a thorough understanding of local thermal-hydraulic conditions, since they affect deposit formation, chemical concentration, and ultimately corrosion. Computational Fluid Dynamics (CFD) can and should play an important role in characterizing the thermal-hydraulic environment and in predicting the consequences of that environment,. The evolution of CFD technology now allows accurate calculation of steam generator thermal-hydraulic conditions and the resulting sludge deposit profiles. Similar calculations are also possible for model boilers, so that tests can be designed to be prototypic of the heat exchanger environment they are supposed to simulate. This paper illustrates the utility of CFD technology by way of examples in each of these two areas. This technology can be further extended to produce more detailed local calculations of the chemical environment in support plate crevices, beneath thick deposits on tubes, and deep in tubesheet sludge piles. Knowledge of this local chemical environment will provide the foundation for development of mechanistic corrosion models, which can be used to optimize inspection and cleaning schedules and focus the search for a viable fix

  8. Mercury Thermal Hydraulic Loop (MTHL) Summary Report

    Energy Technology Data Exchange (ETDEWEB)

    Felde, David K. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Crye, Jason Michael [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wendel, Mark W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Yoder, Jr, Graydon L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Farquharson, George [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Jallouk, Philip A. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); McFee, Marshall T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pointer, William David [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ruggles, Art E. [Univ. of Tennessee, Knoxville, TN (United States); Carbajo, Juan J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2017-03-01

    The Spallation Neutron Source (SNS) is a high-power linear accelerator built at Oak Ridge National Laboratory (ORNL) which incorporates the use of a flowing liquid mercury target. The Mercury Thermal Hydraulic Loop (MTHL) was constructed to investigate and verify the heat transfer characteristics of liquid mercury in a rectangular channel. This report provides a compilation of previously reported results from the water-cooled and electrically heated straight and curved test sections that simulate the geometry of the window cooling channel in the target nose region.

  9. Applied mathematical methods in nuclear thermal hydraulics

    International Nuclear Information System (INIS)

    Ransom, V.H.; Trapp, J.A.

    1983-01-01

    Applied mathematical methods are used extensively in modeling of nuclear reactor thermal-hydraulic behavior. This application has required significant extension to the state-of-the-art. The problems encountered in modeling of two-phase fluid transients and the development of associated numerical solution methods are reviewed and quantified using results from a numerical study of an analogous linear system of differential equations. In particular, some possible approaches for formulating a well-posed numerical problem for an ill-posed differential model are investigated and discussed. The need for closer attention to numerical fidelity is indicated

  10. SBWR core thermal hydraulic analysis during startup

    International Nuclear Information System (INIS)

    Lin, J.H.; Huang, R.L.; Sawyer, C.D.

    1993-01-01

    This paper reports on a thermal hydraulic analysis of the SIMPLIFIED BOILING WATER REACTOR (SBWR) during startup. The potential instability during a SBWR startup has drawn the attention of designers, researchers, and engineers. It has not been a concern for a Boiling Water Reactor (BWR) with forced recirculation; however, for SBWR with natural circulation the concern exists. The concern is about the possibility of a geysering mode oscillation during SBWR startup from a cold temperature and a low system pressure with a low natural circulation flow rate. A thermal hydraulic analysis of the SBWR is performed in simulation of the startup using the TRACG computer code. The temperature, pressure, and reactor power profiles of SBWR during the startup are presented. The results are compared with the data of a natural circulation boiling water reactor, the DODEWAARD plant, in which no instabilities have been observed during many startups. It is shown that a SBWR startup which follows proper procedures, geysering and other modes of oscillations can be avoided

  11. Thermal hydraulic design of PFBR core

    International Nuclear Information System (INIS)

    Roychowdhury, D.G.; Vinayagam, P.P.; Ravichandar, S.C.

    2000-01-01

    The thermal-hydraulic design of core is important in respecting temperature limits while achieving higher outlet temperature. This paper deals with the analytical process developed and implemented for analysing steady state thermal-hydraulics of PFBR core. A computer code FLONE has been developed for optimisation of flow allocation through the subassemblies (SA). By calibrating β n (ratio between the maximum channel temperature rise and SA average temperature rise) values with SUPERENERGY code and using these values in FLONE code, prediction of average and maximum coolant temperature distribution is found to be reasonably accurate. Hence, FLONE code is very powerful design tool for core design. A computer code SAPD has been developed to calculate the pressure drop of fuel and blanket SA. Selection of spacer wire pitch depends on the pressure drop, flow-induced vibration and the mixing characteristics. A parametric study was made for optimisation of spacer wire pitch for the fuel SA. Experimental programme with 19 pin-bundle has been undertaken to find the flow-induced vibration characteristics of fuel SA. Also, experimental programme has been undertaken on a full-scale model to find the pressure drop characteristics in unorificed SA, orifices and the lifting force on the SA. (author)

  12. Thermal Hydraulic Tests for Reactor Core Safety

    Energy Technology Data Exchange (ETDEWEB)

    Moon, S. K.; Baek, W. P.; Chun, S. Y. (and others)

    2007-06-15

    The main objectives of the present project are to resolve the current issues of reactor core thermal hydraulics, to develop an advanced measurement and analytical techniques, and to perform reactor core safety verification tests. 6x6 reflood experiments, various heat transfer experiments using Freon, and experiments on the spacer grids effects on the post-dryout are carried out using spacer grids developed in Korea in order to resolve the current issues of the reactor core thermal hydraulics. In order to develop a reflood heat transfer model, the detailed reflood phenomena are visualized and measured using round tube and 2x2 rod bundle. A detailed turbulent mixing phenomenon for subchannels is measured using advanced measurement techniques such as LDV and PIV. MARS and MATRA codes developed in Korea are assessed, verified and improved using the obtained experimental data. Finally, a systematic quality assurance program and experimental data generation system has been constructed in order to increase the reliability of the experimental data.

  13. Questioning care at the end of life.

    Science.gov (United States)

    Ruopp, Patricia; Good, Mary-Jo Delvecchio; Lakoma, Matthew; Gadmer, Nina M; Arnold, Robert M; Block, Susan D

    2005-06-01

    The goal of the larger study was to explore physicians' emotional responses to the death of their patients; this study analyzed a subset of physician transcripts to elucidate the construct of questioning care, which emerged from the larger study. To analyzes how physicians question care-expressing concern, unease, or uncertainty about treatment decisions and practices, errors, or adverse events-as they attend dying patients. Retrospective interview study of physicians caring for randomly selected deaths on the medical service of a major academic teaching hospital, using qualitative and quantitative measures. SETTING, SUBJECTS: 188 attendings, residents, and interns on the internal medical services of two academic medical centers were part of the larger study. A subsample of 75 physician narratives was selected for qualitative data analysis for this study. Qualitative measures included open-ended questions eliciting physicians' stories of the most recent and a most emotionally powerful patient death they have experienced. Grounded theory was used to analyze physician narratives. Quantitative instruments measured physician attitudes toward end-of-life care and responses to the most recent and most emotional patient death. Physicians question care more frequently in most emotional deaths (42%) than in most recent deaths (34%). Physicians question communication with patients and families and within medical teams, medical judgment and technique, standards of practice, and high-risk treatments, often assigning responsibility for medical management they perceive as inappropriate, futile, overly aggressive, or mistakes in judgment and technique. Responsibility ranges from the distal (the culture of medicine) to the proximal (personal). Frustration, guilt, and anger are more frequently expressed in these narratives when care is questioned. A typology of questioning care emerged from these physicians' narratives that parallels and reflects recent and classic research on

  14. End-of-life care: Indian perspective

    Science.gov (United States)

    Sharma, Himanshu; Jagdish, Vankar; Anusha, Prabhakaran; Bharti, Sharma

    2013-01-01

    According to Hinduism, the main religion of India, the end-of-life (EOL) deals with good and bad death. The WHO definition of palliative care stresses on improving not only the quality of life of patients facing incurable diseases but also their families by providing relief from the pain and suffering that includes the psychosocial and spiritual needs as well. The Indian Society of Palliative Care has been doing a commendable work and appreciable efforts are being done by the Kerala model of delivering the EOL care. The spiritual, ethical issues and ethical challenges raised when the patients are in terminal phase are also reviewed keeping in mind the socio-cultural norms. The Indian Penal Code (IPC) has lacunae, which hamper the physicians from taking proper decision in the EOL care. Some of the sections like IPC 309 are defunct and need to be changed. The Indian Society for Critical Care Medicine has developed a position statement on the patient management of the terminally ill patient in the Intensive Care Unit (ICU) which states that the society should move from the paternalistic model to the share based decision model of the West when deciding the fate of such patients. The literature review on the Indian research on palliative care shows very little emphatic results and the medical under graduates show illiteracy. To strengthen it Medical Council of India has included the palliative care in its curriculum by starting a PG course. Literature review revealed that more research from Indian perspective should be done in this area. This article studies the core issues of developing palliative care in Indian setting keeping in mind the ethical, spiritual and legal issues. PMID:23858271

  15. Multiphase Flow Dynamics 5 Nuclear Thermal Hydraulics

    CERN Document Server

    Kolev, Nikolay Ivanov

    2012-01-01

    The present Volume 5 of the successful book package "Multiphase Flow Dynamics" is devoted to nuclear thermal hydraulics which is a substantial part of nuclear reactor safety. It provides knowledge and mathematical tools for adequate description of the process of transferring the fission heat released in materials due to nuclear reactions into its environment. It step by step introduces into the heat release inside the fuel, temperature fields in the fuels, the "simple" boiling flow in a pipe described using ideas of different complexity like equilibrium, non equilibrium, homogeneity, non homogeneity. Then the "simple" three-fluid boiling flow in a pipe is described by gradually involving the mechanisms like entrainment and deposition, dynamic fragmentation, collisions, coalescence, turbulence. All heat transfer mechanisms are introduced gradually discussing their uncertainty. Different techniques are introduced like boundary layer treatments or integral methods. Comparisons with experimental data at each step...

  16. Multiphase flow dynamics 5 nuclear thermal hydraulics

    CERN Document Server

    Kolev, Nikolay Ivanov

    2015-01-01

    This Volume 5 of the successful book package "Multiphase Flow Dynamics" is devoted to nuclear thermal hydraulics which is a substantial part of nuclear reactor safety. It provides knowledge and mathematical tools for adequate description of the process of transferring the fission heat released in materials due to nuclear reactions into its environment. It step by step introduces into the heat release inside the fuel, temperature fields in the fuels, the "simple" boiling flow in a pipe described using ideas of different complexity like equilibrium, non equilibrium, homogeneity, non homogeneity. Then the "simple" three-fluid boiling flow in a pipe is described by gradually involving the mechanisms like entrainment and deposition, dynamic fragmentation, collisions, coalescence, turbulence. All heat transfer mechanisms are introduced gradually discussing their uncertainty. Different techniques are introduced like boundary layer treatments or integral methods. Comparisons with experimental data at each step demons...

  17. Thermal Hydraulic Design of PWT Accelerating Structures

    CERN Document Server

    Yu, David; Chen Ping; Lundquist, Martin; Luo, Yan

    2005-01-01

    Microwave power losses on the surfaces of accelerating structures will transform to heat which will deform the structures if it is not removed in time. Thermal hydraulic design of the disk and cooling rods of a Plane Wave Transformer (PWT) structure is presented. Experiments to measure the hydraulic (pressure vs flow rate) and cooling (heat removed vs flow rate) properties of the PWT disk are performed, and results compared with simulations using Mathcad models and the COSMOSM code. Both experimental and simulation results showed that the heat deposited on the structure could be removed effectively using specially designed water-cooling circuits and the temperature of the structure could be controlled within the range required.

  18. Thermal hydraulic reactor safety analyses and experiments

    International Nuclear Information System (INIS)

    Holmstroem, H.; Eerikaeinen, L.; Kervinen, T.; Kilpi, K.; Mattila, L.; Miettinen, J.; Yrjoelae, V.

    1989-04-01

    The report introduces the results of the thermal hydraulic reactor safety research performed in the Nuclear Engineering Laboratory of the Technical Research Centre of Finland (VTT) during the years 1972-1987. Also practical applications i.e. analyses for the safety authorities and power companies are presented. The emphasis is on description of the state-of-the-art know how. The report describes VTT's most important computer codes, both those of foreign origin and those developed at VTT, and their assessment work, VTT's own experimental research, as well as international experimental projects and other forms of cooperation VTT has participated in. Appendix 8 contains a comprehensive list of the most important publications and technical reports produced. They present the content and results of the research in detail.(orig.)

  19. An overview on rod-bundle thermal-hydraulic analyses

    International Nuclear Information System (INIS)

    Sha, W.T.

    1980-01-01

    Three methods used in rod-bundle thermal-hydraulic analysis are summarized. These methods are: (1) subchannel analysis, (2) porous medium formulation with volume porosity, surface permeability, distributed resistance and distributed heat source (sink) and, (3) bench-mark rod-bundle thermal-hydraulic analysis using a boundary-fitted coordinate system. Basic limitations and merits of each method are delineated. (orig.)

  20. End-of-Life Nursing Care and Education: End-of-Life Nursing Education: Past and Present.

    Science.gov (United States)

    DʼAntonio, Jocelyn

    The dying experience is forever carried in the life story of those for whom the nurse cares. A goal of end-of-life nursing education is to produce nurses who are comfortable with death and dying and who have had the opportunity to reflect on their thoughts and feelings about end-of-life care. This article reviews the history, development, and teaching methods of end-of-life care, offering recommendations for future education.

  1. PHENIX for beginners

    International Nuclear Information System (INIS)

    Zajc, W.A.; Fachini, P.

    2002-01-01

    An introduction to the PHENIX detector and to the PHENIX physics program is presented. The PHENIX physics results presented here are those from the the first RHIC (Relativistic Heavy Ion Collider) run with Au+Au collisions at √(S NN ) = 130 GeV. A brief overview of the PHENIX detector is provided. The systematic variation with centrality of charged particle multiplicity, transverse energy, identified particle spectra and yield ratios, production of charged hadrons and π0's at high transverse momenta are reported, together with first results on charm production at RHIC

  2. Thermal-hydraulic development a small, simplified, proliferation-resistant reactor

    International Nuclear Information System (INIS)

    Farmer, M. T.; Hill, D. J.; Sienicki, J. J.; Spencer, B. W.; Wade, D. C.

    1999-01-01

    This paper addresses thermal-hydraulics related criteria and preliminary concepts for a small (300 MWt), proliferation-resistant, liquid-metal-cooled reactor system. A main objective is to assess what extent of simplification is achievable in the concepts with the primary purpose of regaining economic competitiveness. The approach investigated features lead-bismuth eutectic (LBE) and a low power density core for ultra-long core lifetime (goal 15 years) with cartridge core replacement at end of life. This potentially introduces extensive simplifications resulting in capital cost and operating cost savings including: (1) compact, modular, pool-type configuration for factory fabrication, (2) 100+% natural circulation heat transport with the possibility of eliminating the main coolant pumps, (3) steam generator modules immersed directly in the primary coolant pool for elimination of the intermediate heat transport system, and (4) elimination of on-site fuel handling and storage provisions including rotating plug. Stage 1 natural circulation model and results are presented. Results suggest that 100+% natural circulation heat transport is readily achievable using LBE coolant and the long-life cartridge core approach; moreover, it is achievable in a compact pool configuration considerably smaller than PRISM A (for overland transportability) and with peak cladding temperature within the existing database range for ferritic steel with oxide layer surface passivation. Stage 2 analysis follows iteration with core designers. Other thermal hydraulic investigations are underway addressing passive, auxiliary heat removal by air cooling of the reactor vessel and the effects of steam generator tube rupture

  3. [End of life and vulnerability, a public health issue].

    Science.gov (United States)

    Boucomont, Aude

    2016-02-01

    End of life and precarity, two words which were linked by the French national observatory for end of life care in its work carried out in 2014. The study provided an overview of current support practices in different areas, highlighting certain lessons to be learned and making recommendations to the different partners involved. Copyright © 2015 Elsevier Masson SAS. All rights reserved.

  4. End-of-life decisions in the intensive care unit

    DEFF Research Database (Denmark)

    Jensen, Hanne Irene

    2012-01-01

    be interdisciplinary, but the literature shows that this is not always the case. Research on end-of-life issues in Danish ICUs is limited. Aim The aims of this thesis were to • Examine Danish practices regarding end-of-life decisions in the ICU. • Examine the opinions of nurses and physicians who work in Danish ICUs...... and decision-making. Hypotheses • Nurses, intensivists, and primary physicians have different experiences of interdisciplinary collaboration regarding end-of-life decision-making in the ICU. • Specific interventions targeting end-of-life decision-making in the ICU, such as interdisciplinary audits......Background When making end-of-life decisions in intensive care units, the different staff groups have different roles in the decision-making process and may not always assess the situation identically. Practice recommendations for withholding or withdrawing therapy state that decisions should...

  5. End of life care - the importance of culture and ethnicity.

    Science.gov (United States)

    Clark, Katherine; Phillips, Jane

    2010-04-01

    Australia is a culturally and ethnically diverse country. Within such diversity there will be differing beliefs systems about death and dying. This may be a challenging prospect for health professionals. This article discusses how cultural diversity may impact care and provides some strategies for the general practitioner when considering the provision of end of life care. This article does not attempt to provide GPs with a prescriptive approach to multicultural care, as this would run the risk of stereotyping individuals. Rather, it discusses the barriers to end of life care among different cultural and ethnic groups, and suggests ways in which to improve understanding of different cultural needs in end of life care.

  6. Thermal-hydraulic design of the 200 MW NHR

    International Nuclear Information System (INIS)

    Li Jincai; Gao Zuying; Xu Baocheng; He Junxiao

    1997-01-01

    The thermal hydraulic design of the 200-MW Nuclear Heating Reactor (NHR), design criteria, design methods, important characteristics and some development results are presented in this paper. (author). 5 refs, 8 figs, 2 tabs

  7. Thermal hydraulic model validation for HOR mixed core fuel management

    International Nuclear Information System (INIS)

    Gibcus, H.P.M.; Vries, J.W. de; Leege, P.F.A. de

    1997-01-01

    A thermal-hydraulic core management model has been developed for the Hoger Onderwijsreactor (HOR), a 2 MW pool-type university research reactor. The model was adopted for safety analysis purposes in the framework of HEU/LEU core conversion studies. It is applied in the thermal-hydraulic computer code SHORT (Steady-state HOR Thermal-hydraulics) which is presently in use in designing core configurations and for in-core fuel management. An elaborate measurement program was performed for establishing the core hydraulic characteristics for a variety of conditions. The hydraulic data were obtained with a dummy fuel element with special equipment allowing a.o. direct measurement of the true core flow rate. Using these data the thermal-hydraulic model was validated experimentally. The model, experimental tests, and model validation are discussed. (author)

  8. Thermal-hydraulic design of the 200 MW NHR

    Energy Technology Data Exchange (ETDEWEB)

    Jincai, Li; Zuying, Gao; Baocheng, Xu; Junxiao, He [Institute of Nuclear Energy and Technology, Tsingua Univ., Beijing (China)

    1997-09-01

    The thermal hydraulic design of the 200-MW Nuclear Heating Reactor (NHR), design criteria, design methods, important characteristics and some development results are presented in this paper. (author). 5 refs, 8 figs, 2 tabs.

  9. End-of-Life Conversation Game Increases Confidence for Having End-of-Life Conversations for Chaplains-in-Training.

    Science.gov (United States)

    Van Scoy, Lauren Jodi; Watson-Martin, Elizabeth; Bohr, Tiffany A; Levi, Benjamin H; Green, Michael J

    2018-04-01

    Discussing end-of-life issues with patients is an essential role for chaplains. Few tools are available to help chaplains-in-training develop end-of-life communication skills. This study aimed to determine whether playing an end-of-life conversation game increases the confidence for chaplain-in-trainings to discuss end-of-life issues with patients. We used a convergent mixed methods design. Chaplains-in-training played the end-of-life conversation game twice over 2 weeks. For each game, pre- and postgame questionnaires measured confidence discussing end-of-life issues with patients and emotional affect. Between games, chaplains-in-training discussed end-of-life issues with an inpatient. One week after game 2, chaplains-in-training were individually interviewed. Quantitative data were analyzed using descriptive statistics and Wilcoxon rank-sum t tests. Content analysis identified interview themes. Quantitative and qualitative data sets were then integrated using a joint display. Twenty-three chaplains-in-training (52% female; 87% Caucasian; 70% were in year 1 of training) completed the study. Confidence scores (scale: 15-75; 75 = very confident) increased significantly after each game, increasing by 10.0 points from pregame 1 to postgame 2 ( P game, and shyness subscale scores decreased significantly after each game. Content analysis found that chaplains-in-training found the game to be a positive, useful experience and reported that playing twice was beneficial (not redundant). Mixed methods analysis suggest that an end-of-life conversation game is a useful tool that can increase chaplain-in-trainings' confidence for initiating end-of-life discussions with patients. A larger sample size is needed to confirm these findings.

  10. Thermal-hydraulic characteristic of the PGV-1000 steam generator

    International Nuclear Information System (INIS)

    Ubra, O.; Doubek, M.

    1995-01-01

    Horizontal steam generators are typical parts of nuclear power plants with pressure water reactor type VVER. By means of this computer program, a detailed thermal-hydraulic study of the horizontal steam generator PGV-1000 has been carried out and a special attention has been paid to the thermal-hydraulics of the secondary side. A set of important steam generator characteristics has been obtained and analyzed. Some of the interesting results of the analysis are presented in the paper. (author)

  11. Culturally Diverse Communities and End-of-Life Care

    Science.gov (United States)

    ... Azen, S.P. (1995). Ethnicity and attitudes toward patient autonomy. JAMA, 274, 820-5 . Phipps, E., True, G., & ... briefly about end-of-life options and neglect culture or values (Tulsky, Fischer, Rose, & Arnold, 1998). Speaking ...

  12. Issues surrounding end-of-life decision-making

    Directory of Open Access Journals (Sweden)

    Tejwani V

    2013-08-01

    Full Text Available Vickram Tejwani,1,* YiFan Wu,1,* Sabrina Serrano,2 Luis Segura,2 Michael Bannon,3 Qi Qian1 1Department of Medicine, Division of Nephrology and Hypertension, 2Mayo Graduate School, 3Department of Trauma, Critical Care, and General Surgery, Mayo Clinic College of Medicine, Rochester, MN, USA *These authors contributed equally to this work Abstract: End-of-life decision-making is a complex process that can be extremely challenging. We describe a 42-year-old woman in an irreversible coma without an advance directive. The case serves to illustrate the complications that can occur in end-of-life decision-making and challenges in resolving difficult futility disputes. We review the role of advance directives in planning end-of-life care, the responsibility and historical performance of patient surrogates, the genesis of futility disputes, and approaches to resolving disputes. Keywords: end-of-life care, advance directive, surrogate, futility dispute, conflict resolution

  13. Wind Turbine Blades: An End of Life Perspective

    DEFF Research Database (Denmark)

    Beauson, Justine; Brøndsted, Povl

    2016-01-01

    In 2016, the first offshore windfarm constructed in the world—located in Denmark, near Ravnsborg—is turning 25 years old, and will soon be decommissioned. After decommissioning, most of the material of the turbine can be recycled; only the composite materials found in the blades represent...... a challenge. This part looks at end of life solutions for this material. Wind turbine blade structure and material are described. The ends of life solutions existing and under development are detailed....

  14. Process management using component thermal-hydraulic function classes

    Science.gov (United States)

    Morman, J.A.; Wei, T.Y.C.; Reifman, J.

    1999-07-27

    A process management expert system where following malfunctioning of a component, such as a pump, for determining system realignment procedures such as for by-passing the malfunctioning component with on-line speeds to maintain operation of the process at full or partial capacity or to provide safe shut down of the system while isolating the malfunctioning component. The expert system uses thermal-hydraulic function classes at the component level for analyzing unanticipated as well as anticipated component malfunctions to provide recommended sequences of operator actions. Each component is classified according to its thermal-hydraulic function, and the generic and component-specific characteristics for that function. Using the diagnosis of the malfunctioning component and its thermal hydraulic class, the expert system analysis is carried out using generic thermal-hydraulic first principles. One aspect of the invention employs a qualitative physics-based forward search directed primarily downstream from the malfunctioning component in combination with a subsequent backward search directed primarily upstream from the serviced component. Generic classes of components are defined in the knowledge base according to the three thermal-hydraulic functions of mass, momentum and energy transfer and are used to determine possible realignment of component configurations in response to thermal-hydraulic function imbalance caused by the malfunctioning component. Each realignment to a new configuration produces the accompanying sequence of recommended operator actions. All possible new configurations are examined and a prioritized list of acceptable solutions is produced. 5 figs.

  15. Process management using component thermal-hydraulic function classes

    Science.gov (United States)

    Morman, James A.; Wei, Thomas Y. C.; Reifman, Jaques

    1999-01-01

    A process management expert system where following malfunctioning of a component, such as a pump, for determining system realignment procedures such as for by-passing the malfunctioning component with on-line speeds to maintain operation of the process at full or partial capacity or to provide safe shut down of the system while isolating the malfunctioning component. The expert system uses thermal-hydraulic function classes at the component level for analyzing unanticipated as well as anticipated component malfunctions to provide recommended sequences of operator actions. Each component is classified according to its thermal-hydraulic function, and the generic and component-specific characteristics for that function. Using the diagnosis of the malfunctioning component and its thermal hydraulic class, the expert system analysis is carried out using generic thermal-hydraulic first principles. One aspect of the invention employs a qualitative physics-based forward search directed primarily downstream from the malfunctioning component in combination with a subsequent backward search directed primarily upstream from the serviced component. Generic classes of components are defined in the knowledge base according to the three thermal-hydraulic functions of mass, momentum and energy transfer and are used to determine possible realignment of component configurations in response to thermal-hydraulic function imbalance caused by the malfunctioning component. Each realignment to a new configuration produces the accompanying sequence of recommended operator actions. All possible new configurations are examined and a prioritized list of acceptable solutions is produced.

  16. Uncharted terrain: preference construction at the end of life.

    Science.gov (United States)

    White, Mary T

    2014-01-01

    Respect for patients' self-determination has long been considered central to efforts to improve end-of-life care, yet efforts to promote advance directives or engage patients in end-of-life discussions are often unsuccessful. In this article, I contend that this is because the shared decision-making approach typically used in healthcare assumes patients' capacity to make rational choices, which is not always possible in end-of-life decisions. Drawing on decision theory, behavioral psychology, and related studies of end-of-life care, I present a growing body of evidence that suggests the novelty, complexity, and uncertainty of end-of-life circumstances make rational and stable preferences difficult to establish. I argue that an effective decision-making approach for the terminally ill must recognize and respond to the unique characteristics of end-of-life choices, including their nonrational dimensions. I conclude with a description of an initiative that appears to do so, resulting in increased patients' satisfaction. Copyright 2014 The Journal of Clinical Ethics. All rights reserved.

  17. PHENIX reports. Final report

    International Nuclear Information System (INIS)

    1998-01-01

    The various tasks outlined in the Statement of Work for the PHENIX Program have been accomplished. Reports were generated which cover the work done. This report is a compilation of the following reports: Progress Report for May 1998; Progress Report for April 1998; PHENIX FEA Mount/Electron Shield Structural Analysis report; Progress Report for February 1998; Progress Report for March 1998; and Progress Report for December 1997 and January 1998

  18. Thermal Hydraulic Integral Effect Tests for Pressurized Water Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Baek, W. P.; Song, C. H.; Kim, Y. S. and others

    2005-02-15

    The objectives of the project are to construct a thermal-hydraulic integral effect test facility and to perform various integral effect tests for design, operation, and safety regulation of pressurized water reactors. During the first phase of this project (1997.8{approx}2002.3), the basic technology for thermal-hydraulic integral effect tests was established and the basic design of the test facility was accomplished: a full-height, 1/300-volume-scaled full pressure facility for APR1400, an evolutionary pressurized water reactor that was developed by Korean industry. Main objectives of the present phase (2002.4{approx}2005.2), was to optimize the facility design and to construct the experimental facility. We have performed following researches: 1) Optimization of the basic design of the thermal-hydraulic integral effect test facility for PWRs - ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) - Reduced height design for APR1400 (+ specific design features of KSNP safety injection systems) - Thermal-hydraulic scaling based on three-level scaling methodology by Ishii et al. 2) Construction of the ATLAS facility - Detailed design of the test facility - Manufacturing and procurement of components - Installation of the facility 3) Development of supporting technology for integral effect tests - Development and application of advanced instrumentation technology - Preliminary analysis of test scenarios - Development of experimental procedures - Establishment and implementation of QA system/procedure.

  19. Symptomatic Control in End-of-Life Patients

    Directory of Open Access Journals (Sweden)

    Mariana Alves

    2017-01-01

    Full Text Available End-of-life patients present a variety of symptoms that cause suffering for them and their respective families. Health professionals throughout their university, internship and medical careers are ill-prepared to manage and improve the quality of life of these patients. This article aims to provide basic skills in the symptomatic management of end-of-life patients, focusing in particular on the control of pain, dyspnoea, fatigue, nausea, vomiting and anorexia. It also aims to draw attention to basic concepts of control concerning refractory symptoms and palliative sedation.

  20. End-of-life decision making in the ICU.

    Science.gov (United States)

    Siegel, Mark D

    2009-03-01

    A large proportion of deaths, particularly in the developed world, follows admission to an ICU. Therefore, end-of life decision making is an essential facet of critical care practice. For intensivists, managing death in the critically ill has become a key professional skill. They must be thoroughly familiar with the ethical framework that guides end-of-life decision making. Decisions should generally be made collaboratively by clinicians partnering with patients' families. Treatment choices should be crafted to meet specific, achievable goals. A rational, empathic approach to working with families should encourage appropriate, mutually satisfactory outcomes.

  1. PHENIX WBS notes

    International Nuclear Information System (INIS)

    1994-02-01

    The Work Breakdown Structure (WBS) Book begins with this Overview section, which contains the high-level summary cost estimate, the cost profile, and the global construction schedule. The summary cost estimate shows the total US cost and the cost in terms of PHENIX construction funds for building the PHENIX detector. All costs in the WBS book are shown in FY 1993 dollars. Also shown are the institutional and foreign contributions, the level of pre-operations funding, and the cost of deferred items. Pie charts are presented at PHENIX WBS level 1 and 2 that show this information. The PHENIX construction funds are shown broken down to PHENIX WBS level 3 items per fiscal year, and the resulting profile is compared to the RHIC target profile. An accumulated difference of the two profiles is also shown. The PHENIX global construction schedule is presented at the end of the Overview section. Following the Overview are sections for each subsystem. Each subsystem section begins with a summary cost estimate, cost profile, and critical path. The total level 3 cost is broken down into fixed costs (M ampersand S), engineering costs (EDIA) and labor costs. Costs are further broken down in terms of PHENIX construction funds, institutional and foreign contributions, pre-operations funding, and deferred items. Also shown is the contingency at level 3 and the level 4 breakdown of the total cost. The cost profile in fiscal years is shown at level 3. The subsystem summaries are followed by the full cost estimate and schedule sheets for that subsystem. These detailed sheets are typically carried down to level 7 or 8. The cost estimate Total, M ampersand S, EDIA, and Labor breakdowns, as well as contingency, for each WBS entry

  2. PHENIX Work Breakdown Structure

    International Nuclear Information System (INIS)

    1994-02-01

    The Work Breakdown Structure (WBS) Book begins with this Overview section, which contains the high-level summary cost estimate, the cost profile, and the global construction schedule. The summary cost estimate shows the total US cost and the cost in terms of PHENIX construction funds for building the PHENIX detector. All costs in the WBS book are shown in FY 1993 dollars. Also shown are the institutional and foreign contributions, the level of pre-operations funding, and the cost of deferred items. Pie charts are presented at PHENIX WBS level 1 and 2 that show this information. The PHENIX construction funds are shown broken down to PHENIX WBS level 3 items per fiscal year, and the resulting profile is compared to the RHIC target profile. An accumulated difference of the two profiles is also shown. The PHENIX global construction schedule is presented at the end of the Overview section. Following the Overview are sections for each subsystem. Each subsystem section begins with a summary cost estimate, cost profile, and critical path. The total level 3 cost is broken down into fixed costs (M ampersand S), engineering costs (EDIA) and labor costs. Costs are further broken down in terms of PHENIX construction funds, institutional and foreign contributions, pre-operations funding, and deferred items. Also shown is the contingency at level 3 and the level 4 breakdown of the total cost. The cost profile in fiscal years is shown at level 3. The subsystem summaries are followed by the full cost estimate and schedule sheets for that subsystem. These detailed sheets are typically carried down to level 7 or 8. The cost estimate shows Total, M ampersand S, EDIA, and Labor breakdowns, as well as contingency, for each WBS entry

  3. Horizontal steam generator PGV-1000 thermal-hydraulic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ubra, O. [Skoda Company, Prague (Switzerland); Doubek, M. [Czech Technical Univ., Prague (Switzerland)

    1995-12-31

    A computer program for the steady state thermal-hydraulic analysis of horizontal steam generator PGV-1000 is presented. The program provides the capability to analyze steam generator PGV-1000 primary side flow and temperature distribution, primary side pressure drops, heat transfer between the primary and secondary sides and multidimensional heat flux distribution. A special attention is paid to the thermal-hydraulics of the secondary side. The code predicts 3-D distribution of the void fraction at the secondary side, mass redistribution under the submerged perforated sheet and the steam generator level profile. By means of developed computer program a detailed thermal-hydraulic study of the PGV-1000 has been carried out. A wide range of calculations has been performed and a set of important steam generator characteristics has been obtained. Some of them are presented in the paper. (orig.). 5 refs.

  4. Horizontal steam generator PGV-1000 thermal-hydraulic analysis

    International Nuclear Information System (INIS)

    Ubra, O.; Doubek, M.

    1995-01-01

    A computer program for the steady state thermal-hydraulic analysis of horizontal steam generator PGV-1000 is presented. The program provides the capability to analyze steam generator PGV-1000 primary side flow and temperature distribution, primary side pressure drops, heat transfer between the primary and secondary sides and multidimensional heat flux distribution. A special attention is paid to the thermal-hydraulics of the secondary side. The code predicts 3-D distribution of the void fraction at the secondary side, mass redistribution under the submerged perforated sheet and the steam generator level profile. By means of developed computer program a detailed thermal-hydraulic study of the PGV-1000 has been carried out. A wide range of calculations has been performed and a set of important steam generator characteristics has been obtained. Some of them are presented in the paper. (orig.)

  5. Horizontal steam generator PGV-1000 thermal-hydraulic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Ubra, O [Skoda Company, Prague (Switzerland); Doubek, M [Czech Technical Univ., Prague (Switzerland)

    1996-12-31

    A computer program for the steady state thermal-hydraulic analysis of horizontal steam generator PGV-1000 is presented. The program provides the capability to analyze steam generator PGV-1000 primary side flow and temperature distribution, primary side pressure drops, heat transfer between the primary and secondary sides and multidimensional heat flux distribution. A special attention is paid to the thermal-hydraulics of the secondary side. The code predicts 3-D distribution of the void fraction at the secondary side, mass redistribution under the submerged perforated sheet and the steam generator level profile. By means of developed computer program a detailed thermal-hydraulic study of the PGV-1000 has been carried out. A wide range of calculations has been performed and a set of important steam generator characteristics has been obtained. Some of them are presented in the paper. (orig.). 5 refs.

  6. Thermal Hydraulic Integral Effect Tests for Pressurized Water Reactors

    International Nuclear Information System (INIS)

    Baek, Won Pil; Song, C. H.; Kim, Y. S.

    2007-02-01

    The objectives of the project are to construct a thermal-hydraulic integral effect test facility and to perform the tests for design, operation, and safety regulation of pressurized water reactors. In the first phase of this project (1997.8∼2002.3), the basic technology for thermal-hydraulic integral effect tests was established and the basic design of the test facility was accomplished. In the second phase (2002.4∼2005.2), an optimized design of the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) was established and the construction of the facility was almost completed. In the third phase (2005.3∼2007.2), the construction and commission tests of the ATLAS are to be completed and some first-phase tests are to be conducted

  7. Thermal hydraulic feasibility assessment of the spent nuclear fuel project

    International Nuclear Information System (INIS)

    Heard, F.J.

    1996-01-01

    A series of analyses have been completed investigating the thermal-hydraulic performance and feasibility of the Spent Nuclear Fuel Project (SNFP) Integrated Process Strategy (IPS). The goal was to develop a series of thermal-hydraulic models that could respond to all process and safety related issues that may arise pertaining to the SNFP, as well as provide a basis for validation of the results. Results show that there is a reasonable envelope for process conditions and requirements that are thermally and hydraulically acceptable

  8. PHENIX Conceptual Design Report

    Energy Technology Data Exchange (ETDEWEB)

    Nagamiya, Shoji; Aronson, Samuel H.; Young, Glenn R.; Paffrath, Leo

    1993-01-29

    The PHENIX Conceptual Design Report (CDR) describes the detector design of the PHENIX experiment for Day-1 operation at the Relativistic Heavy Ion Collider (RHIC). The CDR presents the physics capabilities, technical details, cost estimate, construction schedule, funding profile, management structure, and possible upgrade paths of the PHENIX experiment. The primary goals of the PHENIX experiment are to detect the quark-gluon plasma (QGP) and to measure its properties. Many of the potential signatures for the QGP are measured as a function of a well-defined common variable to see if any or all of these signatures show a simultaneous anomaly due to the formation of the QGP. In addition, basic quantum chromodynamics phenomena, collision dynamics, and thermodynamic features of the initial states of the collision are studied. To achieve these goals, the PHENIX experiment measures lepton pairs (dielectrons and dimuons) to study various properties of vector mesons, such as the mass, the width, and the degree of yield suppression due to the formation of the QGP. The effect of thermal radiation on the continuum is studied in different regions of rapidity and mass. The e[mu] coincidence is measured to study charm production, and aids in understanding the shape of the continuum dilepton spectrum. Photons are measured to study direct emission of single photons and to study [pi][sup 0] and [eta] production. Charged hadrons are identified to study the spectrum shape, production of antinuclei, the [phi] meson (via K[sup +]K[sup [minus

  9. ORIGINAL ARTICLES Medical futility and end-of-life care

    African Journals Online (AJOL)

    2008-04-01

    Apr 1, 2008 ... It is based on the probability of a treatment not having the desired effect ... as empathetic participants in end-of-life decision-making is underscored. .... growing awareness of the limits of medical science's propensity to cure ...

  10. End-of-Life Preferences: A Theory-Driven Inventory

    Science.gov (United States)

    Bonin-Scaon, Sylvie; Munoz Sastre, Maria Teresa; Chasseigne, Gerard; Sorum, Paul C.; Mullet, Etienne

    2009-01-01

    The study aimed at making a theory-driven inventory of end-of-life preferences. Participants were asked about a variety of preferences representing all eight motivational states described in Apter's Metamotivational Theory (AMT; Apter, 2001). Data from a convenience sample of 965 community participants and a convenience sample of 81 persons…

  11. Improving end-of-life care: Recommendations from the IOM.

    Science.gov (United States)

    Dobbins, Elizabeth H

    2016-09-22

    A 2014 consensus report by the Institute of Medicine offers recommendations for healthcare providers to decrease unwanted care and improve the quality of life at the end of life. This article discusses the recommendations of interest to advanced practice registered nurses.

  12. Labelling of end-of-life decisions by physicians

    NARCIS (Netherlands)

    Deyaert, J.; Chambaere, K.; Cohen, J.; Roelands, M.; Deliens, L.

    2014-01-01

    Objectives: Potentially life-shortening medical end-oflife practices (end-of-life decisions (ELDs)) remain subject to conceptual vagueness. This study evaluates how physicians label these practices by examining which of their own practices (described according to the precise act, the intention, the

  13. 47 CFR 25.283 - End-of-life disposal.

    Science.gov (United States)

    2010-10-01

    ... 47 Telecommunication 2 2010-10-01 2010-10-01 false End-of-life disposal. 25.283 Section 25.283 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) COMMON CARRIER SERVICES SATELLITE COMMUNICATIONS... satellite orbit under this part shall be relocated, at the end of its useful life, barring catastrophic...

  14. END-OF-LIFE DECISIONS IN DUTCH NEONATOLOGY

    NARCIS (Netherlands)

    Moratti, Sofia

    2010-01-01

    This contribution describes the regulation of end-of-life decisions in neonatology in the Netherlands. An account is given of the process of formulating rules, which includes a report by the Dutch Association for Paediatrics, two Court rulings, a report by a Consultation Group appointed by the

  15. End-of-life practices: The opinions of undergraduate medical ...

    African Journals Online (AJOL)

    2017-12-01

    Dec 1, 2017 ... illness, injury or other physical or mental condition that, in medical judgment, will .... was all the registered first- to fifth-year medical students at the School ..... patient should have sole responsibility in end-of-life decisions. The.

  16. Continuous subcutaneous infusion of opiates at end-of-life.

    Science.gov (United States)

    Anderson, Stacey L; Shreve, Scott T

    2004-06-01

    To review pertinent controlled trials using the continuous subcutaneous infusion of opioids (CSIO) at end-of-life and offer insight to pharmacists and clinicians into the appropriate use of this route of administration. A MEDLINE search for information regarding the subcutaneous administration of opioids in terminally ill patients (1975-December 2002) was conducted using the key words subcutaneous, narcotics, morphine, hydromorphone, fentanyl, pain, hospices, and palliative care. Additional references were located through review of bibliographies of the articles cited. Case reports and postsurgical studies were excluded. Searches were limited to English-language studies using humans. Experimental and observational studies were evaluated, using prospective trials as the evidence base for conclusions and including pertinent retrospective trials as they relate to the subcutaneous infusion of opioids at end-of-life. CSIO is effective and safe for use in terminal illness. Appropriate situations for consideration of CSIO are when difficulties arise in using the oral route, standard oral opiate therapy has failed adequate trials, the patient has limited intravenous access, adequate supervision of the CSIO is present, and CSIO will not unduly limit the functional activity of the patient. CSIO has a proven role in the management of pain at end-of-life. CSIO should not be considered the first route for administration of opiates, but does offer distinct advantages in the appropriate setting. CSIO continues to be a choice for end-of-life patients and is gradually becoming a standard practice in palliative medicine.

  17. End-of-life-vignettes. A Chaplain's story.

    Science.gov (United States)

    Bodemann, Christina

    2014-03-01

    Julia, a 31-year-old woman, is brain dead after having suffered a cardiac arrest. This article describes a hospital chaplain's journey with her family through the tragedy of letting her die. It addresses the power of pastoral presence and prayer in a situation of loss and grief and the importance of storytelling for everyone involved in Julia's end-of-life care.

  18. Enabling occupation at the end of life: A literature review.

    Science.gov (United States)

    Mills, Katherine; Payne, Angela

    2015-12-01

    Occupation, or meaningful activity, can contribute to the well-being and quality of life of all individuals. It is thus a logical tautology that occupation should be enabled for those at the end of life. Our present review examines current provision of these processes by Occupational Therapist, who can be much-valued members of multidisciplinary palliative care teams. Following a literature search and critical selection, 10 global papers were identified examining occupation and occupational therapy at the end of life in the acute, hospice, and community environments. Universally, there appeared to be a dearth of therapists working in end-of-life care. Provision of palliative care in hospitals was found to be compensatory or rehabilitative. Hospice therapy emerged as pleasingly occupational, though the number of hospice places was disappointingly few. Community literature was sparse, so it proved challenging to draw definitive conclusions. Promising research refracted light on occupation at home; however, it also revealed stretched domiciliary services, where clients are not well informed about the potential scope of occupational therapy. A "good death" involving a quality end-of-life experience is the foundational goal overarching all therapy and medicine in the provision of palliative care. Arguably, an occupation-focused approach provided by therapists meets client needs to enable meaningful experiences in the limited time left to them. Current occupational therapy practice environments are not necessarily achieving these goals in commensurate fashion. There is a need to promote the role of occupational therapy and circumscribe what therapists can offer. Further research is necessitated across all environments and future funding for therapist positions in palliative teams. End-of-life care can be complex and challenging; however, therapists can facilitate fulfillment of client-centered occupational goals. In engaging with personally constructed nuances of meaning

  19. Thermal-Hydraulic Experiments and Modelling for Advanced Nuclear Reactor Systems

    International Nuclear Information System (INIS)

    Song, C. H.; Baek, W. P.; Chung, M. K.

    2007-06-01

    The objectives of the project are to study thermal hydraulic characteristics of advanced nuclear reactor system for evaluating key thermal-hydraulic phenomena relevant to new safety concepts. To meet the research goal, several thermal hydraulic experiments were performed and related thermal hydraulic models were developed with the experimental data which were produced through the thermal hydraulic experiments. The Followings are main research topics: - Multi-dimensional Phenomena in a Reactor Vessel Downcomer - Condensation-induced Thermal Mixing in a Pool - Development of Thermal-Hydraulic Models for Two-Phase Flow - Construction of T-H Data Base

  20. One day, Phenix..

    International Nuclear Information System (INIS)

    2010-01-01

    This book is mainly a collection of pictures taken at the Phenix fast breeder reactor site of Marcoule (France). A brief introduction summarizes the life of the reactor, from the decision of its construction taken in 1968, to its shutdown in 2009. During its first 17 years of existence, the reactor has played the role of demonstrator for the sodium-cooled FBR technology. The experience feedback is enormous. Less than 10 years after its start-up Phenix has demonstrated its breeding capacity at a quasi-industrial scale. Phenix has also demonstrated the feasibility of the minor actinides transmutation. From 1994 to 1997 and from 1998 to 2003 the reactor has been the object of deep renovations allowing its full power operation and the carrying out of irradiation experiments. On March 6, 2009 the reactor was disconnected from the grid. (J.S.)

  1. PHENIX Conceptual Design Report

    International Nuclear Information System (INIS)

    1993-01-01

    The PHENIX Conceptual Design Report (CDR) describes the detector design of the PHENIX experiment for Day-1 operation at the Relativistic Heavy Ion Collider (RHIC). The CDR presents the physics capabilities, technical details, cost estimate, construction schedule, funding profile, management structure, and possible upgrade paths of the PHENIX experiment. The primary goals of the PHENIX experiment are to detect the quark-gluon plasma (QGP) and to measure its properties. Many of the potential signatures for the QGP are measured as a function of a well-defined common variable to see if any or all of these signatures show a simultaneous anomaly due to the formation of the QGP. In addition, basic quantum chromodynamics phenomena, collision dynamics, and thermodynamic features of the initial states of the collision are studied. To achieve these goals, the PHENIX experiment measures lepton pairs (dielectrons and dimuons) to study various properties of vector mesons, such as the mass, the width, and the degree of yield suppression due to the formation of the QGP. The effect of thermal radiation on the continuum is studied in different regions of rapidity and mass. The eμ coincidence is measured to study charm production, and aids in understanding the shape of the continuum dilepton spectrum. Photons are measured to study direct emission of single photons and to study π 0 and η production. Charged hadrons are identified to study the spectrum shape, production of antinuclei, the φ meson (via K + K - decay), jets, and two-boson correlations. The measurements are made down to small cross sections to allow the study of high p T spectra, and J/ψ and Υ production. The PHENIX collaboration consists of over 300 scientists, engineers, and graduate students from 43 institutions in 10 countries. This large international collaboration is supported by US resources and significant foreign resources

  2. Thermal-hydraulic methods in fast reactor safety

    International Nuclear Information System (INIS)

    Weber, D.P.; Briggs, L.L.

    1985-01-01

    Methods for the solution of thermal-hydraulic problems in liquid metal fast breeder reactors (LMFBRs) arising primarily from transient accident analysis are reviewed. Principal emphasis is given to the important phenomenological issues of sodium boiling and fuel motion. Descriptions of representative phenomenological and mathematical models, computational algorithms, advantages and limitations of the approaches, and current research needs and directions are provided

  3. Development of thermal hydraulic evaluation code for CANDU reactors

    International Nuclear Information System (INIS)

    Kim, Man Woong; Yu, Seon Oh; Choi, Yong Seog; Shin, Chull; Hwang, Soo Hyun

    2004-02-01

    To enhance the safety of operating CANDU reactors, the establishment of the safety analysis codes system for CANDU reactors is in progress. As for the development of thermal-hydraulic analysis code for CANDU system, the studies for improvement of evaluation model inside RELAP/CANDU code and the development of safety assessment methodology for GSI (Generic Safety Issues) are in progress as a part of establishment of CANDU safety assessment system. To develop the 3-D thermal-hydraulic analysis code for moderator system, the CFD models for analyzing the CANDU-6 moderator circulation are developed. One model uses a structured grid system with the porous media approach for the 380 Calandria tubes in the core region. The other uses a unstructured grid system on the real geometry of 380 Calandria tubes, so that the detailed fluid flow between the Calandria tubes can be observed. As to the development of thermal-hydraulic analysis code for containment, the study on the applicability of CONTAIN 2.0 code to a CANDU containment was conducted and a simulation of the thermal-hydraulic phenomena during the accident was performed. Besides, the model comparison of ESFs (Engineered Safety Features) inside CONTAIN 2.0 code and PRESCON code has also conducted

  4. Current and anticipated uses of thermal hydraulic codes in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Kyung-Doo; Chang, Won-Pyo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1997-07-01

    In Korea, the current uses of thermal hydraulic codes are categorized into 3 areas. The first application is in designing both nuclear fuel and NSSS. The codes have usually been introduced based on the technology transfer programs agreed between KAERI and the foreign vendors. Another area is in the supporting of the plant operations and licensing by the utility. The third category is research purposes. In this area assessments and some applications to the safety issue resolutions are major activities using the best estimate thermal hydraulic codes such as RELAP5/MOD3 and CATHARE2. Recently KEPCO plans to couple thermal hydraulic codes with a neutronics code for the design of the evolutionary type reactor by 2004. KAERI also plans to develop its own best estimate thermal hydraulic code, however, application range is different from KEPCO developing code. Considering these activities, it is anticipated that use of the best estimate hydraulic analysis code developed in Korea may be possible in the area of safety evaluation within 10 years.

  5. Thermal-hydraulic research plan for Babcock and Wilcox plants

    International Nuclear Information System (INIS)

    Lee, R.Y.

    1988-02-01

    This document presents a plan for thermal-hydraulic research for Babcock and Wilcox designed reactor systems. It describes the technical issues, regulatory needs, and the research necessary to address these needs. The plan also discusses the relationship between current and proposed research, and provides a tentative schedule to complete the required work

  6. Pain relief at the end of life: nurses' experiences regarding end-of-life pain relief in patients with dementia.

    Science.gov (United States)

    Brorson, Hanna; Plymoth, Henrietta; Örmon, Karin; Bolmsjö, Ingrid

    2014-03-01

    Patients with dementia receive suboptimal palliative care, and this patient group is at risk to have pain at the end of life. Because communicative impairments are common in this patient group, nurses play an important caregiver role in identifying, assessing, and relieving patients' pain. This study aimed to describe nurses' experiences regarding end-of-life pain relief in patients with dementia. This descriptive exploratory qualitative study was based on seven semistructured interviews. Burnard's content analysis inspired the data analysis. Two main categories were identified: (1) nurses' experience of difficulties concerning pain relief and (2) nurses' experience of resources concerning pain relief. Nurses experienced difficulties, such as feeling of powerlessness because of difficulties in obtaining adequate prescriptions for analgesics, ethical dilemmas, feeling of inadequacy because analgesia did not have the desired effect, and a feeling of not being able to connect with the patient. Factors, including knowledge about the patient, professional experience, utilization of pain assessment tools, interpersonal relationships, and interprofessional cooperation, served as resources and enabled end-of-life pain relief. The results of this study highlight the complexity of pain relief in patients with dementia at the end of life from a nursing perspective. The inability of patients with dementia to verbally communicate their pain makes them a vulnerable patient group, dependent on their caregivers. Knowing the life story of the patient, professional experience, teamwork based on good communication, and use of a pain assessment tool were reported by the nurses to improve pain relief at the end of life for patients with dementia. Copyright © 2014 American Society for Pain Management Nursing. Published by Elsevier Inc. All rights reserved.

  7. Development of regulatory technology for thermal-hydraulic safety analysis

    International Nuclear Information System (INIS)

    Bang, Young Seok; Lee, S. H.; Ryu, Y. H.

    2001-02-01

    The present study aims to develop the regulation capability in thermal-hydraulic safety analysis which was required for the reasonable safety regulation in the current NPP, the next generation reactors, and the future-type reactors. The fourth fiscal year of the first phase of the research was focused on the following research topics: Investigation on the current status of the thermal-hydraulic safety analysis technology outside and inside of the country; Review on the improved features of the thermal-hydraulic safety analysis regulatory audit code, RELAP5/MOD3; Assessments of code with LOFT L9-3 ATWS experiment and LSTF SB-SG-10 multiple SGTR experiment; Application of the RELAP5/CANDU code to analyses of SLB and LBLOCA and evaluation of its effect on safety; Application of the code to IAEA PHWR ISP analysis; Assessments of RELAP5 and TRAC with UPTF downcomer injection test and Analysis of LBLOCA with RELAP5 for the performance evaluation of KNGR DVI; Setup of a coupled 3-D kinetics and thermal-hydraulics and application it to a reactivity accident analysis; and Extension of database and improvement of plant input decks. For supporting the resolution of safety issues, loss of RHR event during midloop operation was analyzed for Kori Unit 3, issues on high burnup fuel were reviewed and performance of FRAPCON-3 assessed. Also MSLB was analyzed to figure out the sensitivity of downcomer temperature supporting the PTS risk evaluation of Kori Unit 1. Thermal stratification in pipe was analyzed using the method proposed. And a method predicting the thermal-hydraulic performance of IRWST of KNGR was explored. The PWR ECCS performance criteria was issued as a MOST Article 200-19.and a regulatory guide on evaluation methodology was improved to cover concerns raised from the related licensing review process

  8. Thermal-hydraulic analysis for wire-wrapped PWR cores

    Energy Technology Data Exchange (ETDEWEB)

    Diller, P. [General Electric Company, 3901 Castle Hayne Rd., Wilmington, NC 28401 (United States)], E-mail: pdiller@gmail.com; Todreas, N. [Massachusetts Institute of Technology, Cambridge, MA 02139 (United States)], E-mail: todreas@mit.edu; Hejzlar, P. [Massachusetts Institute of Technology, Cambridge, MA 02139 (United States)

    2009-08-15

    This work focuses on the steady-state and transient thermal-hydraulic analyses for PWR cores using wire wraps in a hexagonal array with either U (45% w/o)-ZrH{sub 1.6} (referred to as U-ZrH{sub 1.6}) or UO{sub 2} fuels. Equivalences (thermal-hydraulic and neutronic) were created between grid spacer and wire wrap designs, and were used to apply results calculated for grid spacers to wire wrap designs. Design limits were placed on the pressure drop, critical heat flux (CHF), fuel and cladding temperature and vibrations. The vibrations limits were imposed for flow-induced vibrations (FIV) and thermal-hydraulic vibrations (THV). The transient analysis examined an overpower accident, loss of coolant accident (LOCA) and loss of flow accident (LOFA). The thermal-hydraulic performance of U-ZrH{sub 1.6} and UO{sub 2} were found very similar. Relative to grid spacer designs, wire wrap designs were found to have smaller fretting wear, substantially lower pressure drop and higher CHF. As a result, wire wrap cores were found to offer substantially higher maximum powers than grid spacer cores, allowing for a 25% power increase relative to the grid spacer uprate [Shuffler, C.A., Malen, J.A., Trant, J.M., Todreas, N.E., 2009a. Thermal-hydraulic analysis for grid supported and inverted fueled PWR cores. Nuclear Technology (this special issue devoted to hydride fuel in LWRs)] and a 58% power increase relative to the reference core.

  9. Nuclear power plant thermal-hydraulic performance research program plan

    International Nuclear Information System (INIS)

    1988-07-01

    The purpose of this program plan is to present a more detailed description of the thermal-hydraulic research program than that provided in the NRC Five-Year Plan so that the research plan and objectives can be better understood and evaluated by the offices concerned. The plan is prepared by the Office of Nuclear Regulatory Research (RES) with input from the Office of Nuclear Reactor Regulation (NRR) and updated periodically. The plan covers the research sponsored by the Reactor and Plant Systems Branch and defines the major issues (related to thermal-hydraulic behavior in nuclear power plants) the NRC is seeking to resolve and provides plans for their resolution; relates the proposed research to these issues; defines the products needed to resolve these issues; provides a context that shows both the historical perspective and the relationship of individual projects to the overall objectives; and defines major interfaces with other disciplines (e.g., structural, risk, human factors, accident management, severe accident) needed for total resolution of some issues. This plan addresses the types of thermal-hydraulic transients that are normally considered in the regulatory process of licensing the current generation of light water reactors. This process is influenced by the regulatory requirements imposed by NRC and the consequent need for technical information that is supplied by RES through its contractors. Thus, most contractor programmatic work is administered by RES. Regulatory requirements involve the normal review of industry analyses of design basis accidents, as well as the understanding of abnormal occurrences in operating reactors. Since such transients often involve complex thermal-hydraulic interactions, a well-planned thermal-hydraulic research plan is needed

  10. DESIGN CONSIDERATIONS UPON PRODUCT END-OF-LIFE OPTIONS

    Directory of Open Access Journals (Sweden)

    BARSAN Lucian

    2016-11-01

    Full Text Available The paper presents some considerations about the necessity of evaluating the environmental impact of a product during its entire life. The present situation (economic, social and ecologic imposes solutions to reduce this impact as a result of an analysis performed during all stages of the life cycle. This paper focuses on design solutions with consequences in the last stage, the end-of-life. Reusing products, with, or without remanufacturing and recycling the materials from products that cannot be reused represent some options analysed in this paper. The end-of-life options should be known even from the beginning of the design process and should be included as design objectives or, at least as constrictions. Considering them as human needs would naturally include them in the requirements list.

  11. Doctors' learning experiences in end-of-life care

    DEFF Research Database (Denmark)

    Fosse, Anette; Ruths, Sabine; Malterud, Kirsti

    2017-01-01

    death could even be welcomed. Through challenging dialogues dealing with family members’ hope and trust, they learnt how to adjust words and decisions according to family and patient’s life story. Interdisciplinary role models helped them balance uncertainty and competence in the intermediate position......Background: Doctors often find dialogues about death difficult. In Norway, 45% of deaths take place in nursing homes. Newly qualified medical doctors serve as house officers in nursing homes during internship. Little is known about how nursing homes can become useful sites for learning about end-of-life...... care. The aim of this study was to explore newly qualified doctors’ learning experiences with end-of-life care in nursing homes, especially focusing on dialogues about death. Methods: House officers in nursing homes (n = 16) participated in three focus group interviews. Interviews were audiotaped...

  12. REUSE OF AUTOMOTIVE COMPONENTS FROM DISMANTLED END OF LIFE VEHICLES

    Directory of Open Access Journals (Sweden)

    Piotr NOWAKOWSKI

    2013-12-01

    Full Text Available The problem of recycling end of life automotive vehicles is serious worldwide. It is one of the most important streams of waste in developed countries. It has big importance as recycling potential of raw materials content in automotive vehicles is valuable. Different parts and assemblies after dismantling can also be reused in vehicles where replacement of specific component is necessary. Reuse of the components should be taken into consideration in selecting the vehicles dismantling strategy. It also complies with European Union policy concerning end of life vehicles (ELV. In the paper it is presented systematic approach to dismantling strategies including disassembly oriented on further reuse of components. It is focused on decision making and possible benefits calculation from economic and environmental point of view.

  13. Thermal hydraulic tests for reactor safety system -Research on the improvement of nuclear safety-

    International Nuclear Information System (INIS)

    Chung, Moon Ki; Park, Chun Kyeong; Yang, Seon Kyu; Chung, Chang Hwan; Chun, Shee Yeong; Song, Cheol Hwa; Chun, Hyeong Gil; Chang, Seok Kyu; Chung, Heung Joon; Won, Soon Yeon; Cho, Yeong Ro; Kim, Bok Deuk; Min, Kyeong Ho

    1994-07-01

    The present research aims at the development of the thermal hydraulic verification test technology for the reactor safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. (Author)

  14. 78 FR 8202 - Meeting of the Joint ACRS Subcommittees on Thermal Hydraulic Phenomena and Materials, Metallurgy...

    Science.gov (United States)

    2013-02-05

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS) Meeting of the Joint ACRS Subcommittees on Thermal Hydraulic Phenomena and Materials, Metallurgy and Reactor Fuels; Notice of Meeting The Joint ACRS Subcommittees on Thermal Hydraulic Phenomena and Materials, Metallurgy and...

  15. Palliative and end-of-life care in South Dakota.

    Science.gov (United States)

    Minton, Mary E; Kerkvliet, Jennifer L; Mitchell, Amanda; Fahrenwald, Nancy L

    2014-05-01

    Geographical disparities play a significant role in palliative and end-of-life care access. This study assessed availability of palliative and end of life (hospice) care in South Dakota. Grounded in a conceptual model of advance care planning, this assessment explored whether South Dakota health care facilities had contact persons for palliative care, hospice services, and advance directives; health care providers with specialized training in palliative and hospice care; and a process for advance directives and advance care planning. Trained research assistants conducted a brief telephone survey. Of 668 health care eligible facilities, 455 completed the survey for a response rate of 68 percent (455 out of 668). Over one-half of facilities had no specific contact person for palliative care, hospice services and advance directives. Nursing homes reported the highest percentage of contacts for palliative care, hospice services and advance directives. Despite a lack of a specific contact person, nearly 75 percent of facilities reported having a process in place for addressing advance directives with patients; slightly over one-half (53 percent) reported having a process in place for advance care planning. Of participating facilities, 80 percent had no staff members with palliative care training, and 73 percent identified lack of staff members with end-of-life care training. Palliative care training was most commonly reported among hospice/home health facilities (45 percent). The results of this study demonstrate a clear need for a health care and allied health care workforce with specialized training in palliative and end-of-life care.

  16. [Precarity, vulnerability, anticipating end-of-life care at home].

    Science.gov (United States)

    Bonneval, Camille

    2016-02-01

    Many patients want to end their life at home. Care teams adapt to these wishes and organise a form of treatment which blends safety of care and the respect of the expectations of the patients and family members. When factors of precarity increase the vulnerability inherent to the end of life, caregivers anticipate and support as best as they can the difficulties encountered as testified by a hospital at home team in Dax. Copyright © 2015 Elsevier Masson SAS. All rights reserved.

  17. Use of Simulation in End-of-Life Care Education.

    Science.gov (United States)

    Grabow, Debra

    Death and dying encompasses the period when individuals present with a limited prognosis and are near death or have recently died. Using simulation to educate nurses on end-of-life (EOL) care helps focus more on the needs of the learner rather than the patient, and allows the learner to process feelings in preparation for a real experience. Incorporating simulation with a spiritual perspective is essential and needed in EOL nursing care.

  18. Team Leadership and Cancer End-of-Life Decision Making.

    Science.gov (United States)

    Waldfogel, Julie M; Battle, Dena J; Rosen, Michael; Knight, Louise; Saiki, Catherine B; Nesbit, Suzanne A; Cooper, Rhonda S; Browner, Ilene S; Hoofring, Laura H; Billing, Lynn S; Dy, Sydney M

    2016-11-01

    End-of-life decision making in cancer can be a complicated process. Patients and families encounter multiple providers throughout their cancer care. When the efforts of these providers are not well coordinated in teams, opportunities for high-quality, longitudinal goals of care discussions can be missed. This article reviews the case of a 55-year-old man with lung cancer, illustrating the barriers and missed opportunities for end-of-life decision making in his care through the lens of team leadership, a key principle in the science of teams. The challenges demonstrated in this case reflect the importance of the four functions of team leadership: information search and structuring, information use in problem solving, managing personnel resources, and managing material resources. Engaging in shared leadership of these four functions can help care providers improve their interactions with patients and families concerning end-of-life care decision making. This shared leadership can also produce a cohesive care plan that benefits from the expertise of the range of available providers while reflecting patient needs and preferences. Clinicians and researchers should consider the roles of team leadership functions and shared leadership in improving patient care when developing and studying models of cancer care delivery.

  19. A relational ethical approach to end-of-life delirium.

    Science.gov (United States)

    Wright, David Kenneth; Brajtman, Susan; Macdonald, Mary Ellen

    2014-08-01

    Delirium is a condition of acute onset and fluctuating course in which a person's level of consciousness and cognition become disturbed. Delirium is a common and distressing phenomenon in end-of-life care, yet it is underrecognized and undertreated. In this article, we review qualitative descriptions of the delirium experience in end-of-life care, found through a systematic search of academic databases, to generate insight into the intersubjective nature of the delirium experience. Our analysis of retrieved studies advances an understanding of the relational ethical dimensions of this phenomenon, that is, how delirium is lived by patients, families, and health care providers and how it affects the relationships and values at stake. We propose three themes that explain the distressing nature of delirium in palliative care: 1) experiences of relational tension; 2) challenges in recognizing the delirious person; and 3) struggles to interpret the meaning of delirious behaviors. By approaching end-of-life delirium from a perspective of relational ethics, attention is focused on the implications for the therapeutic relationship with patients and families when delirium becomes part of the dying trajectory. Copyright © 2014 American Academy of Hospice and Palliative Medicine. Published by Elsevier Inc. All rights reserved.

  20. Spiritual distress of military veterans at the end of life.

    Science.gov (United States)

    Chang, Bei-Hung; Stein, Nathan R; Skarf, Lara M

    2015-06-01

    Although combat experiences can have a profound impact on individuals' spirituality, there is a dearth of research in this area. Our recent study indicates that one unique spiritual need of veterans who are at the end of life is to resolve distress caused by combat-related events that conflict with their personal beliefs. This study sought to gain an understanding of chaplains' perspectives on this type of spiritual need, as well as the spiritual care that chaplains provide to help veterans ease this distress. We individually interviewed five chaplains who have provided spiritual care to veterans at the end of life in a Veterans Administration hospital. The interviews were recorded, transcribed, and analyzed based on "grounded theory." Chaplains reported that they frequently encounter veterans at the end of life who are still suffering from thoughts or images of events that occurred during their military career. Although some veterans are hesitant to discuss their experiences, chaplains reported that they have had some success with helping the veterans to open up. Additionally, chaplains reported using both religious (e.g., confessing sins) and nonreligious approaches (e.g., recording military experience) to help veterans to heal. Our pilot study provides some insight into the spiritual distress that many military veterans may be experiencing, as well as methods that a chaplain can employ to help these veterans. Further studies are needed to confirm our findings and to examine the value of integrating the chaplain service into mental health care for veterans.

  1. The significance of end-of-life dreams and visions.

    Science.gov (United States)

    Grant, Pei; Wright, Scott; Depner, Rachel; Luczkiewicz, Debra

    End-of-life dreams and visions (ELDVs) have been well documented through history and across cultures. They appear to affect both dying people and their families deeply, and may be a source of profound meaning and comfort. The aims of the study were to; document hospice patients' ELDV experiences over time using a daily survey, examine the content and subjective significance of ELDVs, and relate the prevalence, content and significance of end-of-life experiences over time until death. Patients (n = 66) in a hospice inpatient unit, between January 2011 and July 2012, were interviewed daily. The interview contained closed questions about the content, frequency and level of comfort or distress of dreams and visions. Most participants reported at least one dream or vision and almost half of the dreams and visions occurred during sleep. Nearly all patients reported that their experience felt real. The most common content featured deceased friends and relatives, followed by living friends and relatives. As participants approached death, comforting dreams and visions of the deceased became more prevalent. End-of-life dreams and visions are commonly experienced during dying. These dreams and visions may be a profound source of potential meaning and comfort to the dying.

  2. Contribution to the study of thermal-hydraulic problems in nuclear reactors; Contribution a l`etude de problemes de thermohydraulique dans les reacteurs nucleaires

    Energy Technology Data Exchange (ETDEWEB)

    Cognet, G

    1998-07-07

    In nuclear reactors, whatever the type considered, Pressurized Water Water Reactors (PWRs), Fast Breeder reactors (FBRs)..., thermal-hydraulics, the science of fluid mechanics and thermal behaviour, plays an essential role, both in nominal operating and accidental conditions. Fluid can either be the primary fluid (liquid or gas) or a very specific fluid called corium, which, in case of severe accident, could result from core and environning structure melting. The work reported here represents a 20-year contribution to thermal-hydraulic issues which could occur in FBRs and PWRs. Working on these two types of reactors, both in nominal and severe accident situations, has allowed me to compare the problems and to realize the importance of communication between research teams. The evolution in the complexity of studied problems, unavoidable in order to reduce costs and significantly improve safety, has led me from numerical modelling of single-phase flow turbulence to high temperature real melt experiments. The difficulties encountered in understanding the observed phenomena and in increasing experimental databases for computer code qualification have often entailed my participation in specific measurement device developments or adaptations, in particular non-intrusive devices generally based on optical techniques. Being concerned about the end-use of this research work, I actively participated in `in-situ` thermalhydraulic experiments in the FBRs: Phenix and Super-Phenix, of which I appreciated their undeniable scientific contribution. In my opinion, the thermal-hydraulic questions related to severe accidents are the most complex as they are at the cross-roads of several scientific specialities. Consequently, they require a multi-disciplinary approach and a continuous see-saw motion between experimentalists and modelling teams. After a brief description of the various problems encountered, the main ones are reported. Finally, the importance for research teams to

  3. FONESYS: The FOrum and NEtwork of SYStem Thermal-Hydraulic Codes in Nuclear Reactor Thermal-Hydraulics

    Energy Technology Data Exchange (ETDEWEB)

    Ahn, S.H., E-mail: k175ash@kins.re.kr [Korea Institute of Nuclear Safety (KINS) (Korea, Republic of); Aksan, N., E-mail: nusr.aksan@gmail.com [University of Pisa San Piero a Grado Nuclear Research Group (GRNSPG) (Italy); Austregesilo, H., E-mail: henrique.austregesilo@grs.de [Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) (Germany); Bestion, D., E-mail: dominique.bestion@cea.fr [Commissariat à l’énergie atomique et aux énergies alternatives (CEA) (France); Chung, B.D., E-mail: bdchung@kaeri.re.kr [Korea Atomic Energy Research Institute (KAERI) (Korea, Republic of); D’Auria, F., E-mail: f.dauria@ing.unipi.it [University of Pisa San Piero a Grado Nuclear Research Group (GRNSPG) (Italy); Emonot, P., E-mail: philippe.emonot@cea.fr [Commissariat à l’énergie atomique et aux énergies alternatives (CEA) (France); Gandrille, J.L., E-mail: jeanluc.gandrille@areva.com [AREVA NP (France); Hanninen, M., E-mail: markku.hanninen@vtt.fi [VTT Technical Research Centre of Finland (VTT) (Finland); Horvatović, I., E-mail: i.horvatovic@ing.unipi.it [University of Pisa San Piero a Grado Nuclear Research Group (GRNSPG) (Italy); Kim, K.D., E-mail: kdkim@kaeri.re.kr [Korea Atomic Energy Research Institute (KAERI) (Korea, Republic of); Kovtonyuk, A., E-mail: a.kovtonyuk@ing.unipi.it [University of Pisa San Piero a Grado Nuclear Research Group (GRNSPG) (Italy); Petruzzi, A., E-mail: a.petruzzi@ing.unipi.it [University of Pisa San Piero a Grado Nuclear Research Group (GRNSPG) (Italy)

    2015-01-15

    Highlights: • We briefly presented the project called Forum and Network of System Thermal-Hydraulics Codes in Nuclear Reactor Thermal-Hydraulics (FONESYS). • We presented FONESYS participants and their codes. • We explained FONESYS projects motivation, its main targets and working modalities. • We presented FONESYS position about projects topics and subtopics. - Abstract: The purpose of this article is to present briefly the project called Forum and Network of System Thermal-Hydraulics Codes in Nuclear Reactor Thermal-Hydraulics (FONESYS), its participants, the motivation for the project, its main targets and working modalities. System Thermal-Hydraulics (SYS-TH) codes, also as part of the Best Estimate Plus Uncertainty (BEPU) approaches, are expected to achieve a more-and-more relevant role in nuclear reactor technology, safety and design. Namely, the number of code-users can easily be predicted to increase in the countries where nuclear technology is exploited. Thus, the idea of establishing a forum and a network among the code developers and with possible extension to code users has started to have major importance and value. In this framework the FONESYS initiative has been created. The main targets of FONESYS are: • To promote the use of SYS-TH Codes and the application of the BEPU approaches. • To establish acceptable and recognized procedures and thresholds for Verification and Validation (V and V). • To create a common ground for discussing envisaged improvements in various areas, including user-interface, and the connection with other numerical tools, including Computational Fluid Dynamics (CFD) Codes.

  4. A Multinational perspective to managing end-of-life electronics

    Energy Technology Data Exchange (ETDEWEB)

    Herold, M.

    2007-07-01

    This thesis focuses on how multinational electronics manufacturers manage used products in the EU, USA, Japan and China. Managing used or end-of-life products has interesting environmental and commercial implications. Recovering end-of-life products can reduce the environmental effects of disposal, raw material extraction, transport, and production. Whereas the commercial effects include image benefits and savings on raw material costs. Manufacturer involvement in end-of-life management is especially topical in the electronics industry, which is the focus of this thesis. Electronics products, such as TVs and computers, have been targeted with extended producer responsibility (EPR) legislation in different countries across the world. EPR is an environmental policy approach that forces manufacturers to take physical and/or financial responsibility for end-of-life products. The main objective of this dissertation was to increase understanding of how multinational manufacturers manage end-of-life products in the EU, in the USA, and in China and Japan, and the regional and company-specific factors explain their levels of involvement. This study consisted of an inductive 16-case multiple case study. The products and companies included in the study were as follows: Refrigerators (Bosch und Siemens Hausgeraete, Electrolux, Whirlpool); TVs (Samsung, Philips, Hitachi); PCs (Hewlett Packard, NEC, Fujitsu Limited and Fujitsu-Siemens Computers and an anonymous company, Alpha Computers); Mobile phones (Nokia, Motorola, Samsung); Telecommunication network equipment (Nokia, Motorola, Huawei). A manufacturer's level of involvement in end-of-life management can be characterized in terms of the level of organizational capabilities. These capabilities range from none to running a treatment facility and recovering value from own branded products. Levels in between can be characterized by outsourcing end-of-life management to industry-wide schemes, managing contracts for treating

  5. Optimised Iteration in Coupled Monte Carlo - Thermal-Hydraulics Calculations

    Science.gov (United States)

    Hoogenboom, J. Eduard; Dufek, Jan

    2014-06-01

    This paper describes an optimised iteration scheme for the number of neutron histories and the relaxation factor in successive iterations of coupled Monte Carlo and thermal-hydraulic reactor calculations based on the stochastic iteration method. The scheme results in an increasing number of neutron histories for the Monte Carlo calculation in successive iteration steps and a decreasing relaxation factor for the spatial power distribution to be used as input to the thermal-hydraulics calculation. The theoretical basis is discussed in detail and practical consequences of the scheme are shown, among which a nearly linear increase per iteration of the number of cycles in the Monte Carlo calculation. The scheme is demonstrated for a full PWR type fuel assembly. Results are shown for the axial power distribution during several iteration steps. A few alternative iteration method are also tested and it is concluded that the presented iteration method is near optimal.

  6. Thermal-hydraulic modeling of porous bed reactors

    International Nuclear Information System (INIS)

    Araj, K.J.; Nourbakhsh, H.P.

    1987-01-01

    Optimum design of nuclear reactor core requires an iterative approach between the thermal-hydraulic, neutronic and operational analysis. This paper concentrates on the thermal-hydraulic behavior of a hydrogen cooled, small particle bed reactor (PBR). The PBR core, modeled here, consists of a hexagonal array of fuel elements embedded in a moderator matrix. The fuel elements are annular packed beds of fuel particles held between two porous cylindrical frits. These particles, 500 to 600 μm in diameter, have a uranium carbide core, which is coated by two layers of graphite and an outer coating of zirconium carbide. Coolant flow, radially inward, from the cold frit through the packed bed and hot frit and axially out the channel, formed by the hot frit, to a common plenum. 5 refs., 1 fig., 2 tabs

  7. Thermal hydraulic model descrition of TASS/SMR

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Han Young; Kim, H. C.; Chung, Y. J.; Lim, H. S.; Yang, S. H

    2001-04-01

    The TASS/SMR code has been developed for the safety analysis of SMART. The governing equations were applied only to the primary coolant system in TASS which had been developed at KAERI. In TASS/SMR, the solution method is improved so that the primary and secondary coolant systems are solved simultaneously. Besides the solution method, thermal-hydraulic models are incorporated, in TASS/SMR, such as non-condensible gas model, helical steam generator heat transfer model, and passive residual heat removal system (PRHRS) heat transfer model for the application to SMART. The governing equtions of TASS/SMR are based on the drift-flux model so that the accidents and transients accompaning with two-phase flow can be analized. This report describes the governing equations and solution methods used in TASS/SMR and also includes the description for the thermal hydraulic models for SMART design.

  8. Simulation of Thermal Hydraulic at Supercritical Pressures with APROS

    Energy Technology Data Exchange (ETDEWEB)

    Kurki, Joona [VTT Technical Research Centre of Finland, P.O. Box 1000, FI02044 VTT (Finland)

    2008-07-01

    The proposed concepts for the fourth generation of nuclear reactors include a reactor operating with water at thermodynamically supercritical state, the Supercritical Water Reactor (SCWR). For the design and safety demonstrations of such a reactor, the possibility to accurately simulate the thermal hydraulics of the supercritical coolant is an absolute prerequisite. For this purpose, the one-dimensional two-phase thermal hydraulics solution of APROS process simulation software was developed to function at the supercritical pressure region. Software modifications included the redefinition of some parameters that have physical significance only at the subcritical pressures, improvement of the steam tables, and addition of heat transfer and friction correlations suitable for the supercritical pressure region. (author)

  9. Thermal hydraulic simulation of the CANDU nuclear reactor

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Athos M.S.S. de; Ramos, Mario C.; Costa, Antonella L.; Fernandes, Gustavo H.N., E-mail: athos1495@yahoo.com.br [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil). Departamento de Engenharia Nuclear; Instituto Nacional de Ciência e Tecnologia de Reatores Nucleares Inovadores (INCT/CNPq), Rio de janeiro, RJ (Brazil)

    2017-07-01

    The CANDU (Canada Deuterium Uranium) is a Canadian-designed power reactor of PHWR type (Pressurized Heavy Water Reactor) that uses heavy water (deuterium oxide) for moderator and coolant, and natural uranium for fuel. There are about 47 reactors of this type in operation around the world generating more than 23 GWe, highlighting the importance of this kind of device. In this way, the main purpose of this study is to develop a thermal hydraulic model for a CANDU reactor to aggregate knowledge in this line of research. In this way, a core modeling was performed using RELAP5-3D code. Results were compared with reference data to verify the model behavior in steady state operation. Thermal hydraulic parameters as temperature, pressure and mass flow rate were verified and the results are in good agreement with reference data, as it is being presented in this work. (author)

  10. Thermal-hydraulic tests for reactor safety system

    International Nuclear Information System (INIS)

    Chun, Se Young; Chung, Moon Ki; Baek, Won Pil

    2002-05-01

    Tests for the safety depressurization system, Sparger adopted for the Korean next generation reactor, APR1400 are carried out for several geometries with the B and C (Blowdown and Condensation) facility in the condition of high temperature and pressure and with a small test facility in the condition of atmospheric temperature and pressure. Tests for the critical heat flux are performed with the RCS(Reactor Coolant System) facility as well as with the Freon CHF Loop in the condition of high temperature and pressure. The atmospheric temperature and pressure facility is utilized for development of the high standard thermal hydraulic measurement technology. The optical method is developed to measure the local thermal-hydraulic behavior for the single and two-phase boiling phenomena

  11. Equipping simulators with an advanced thermal hydraulics model EDF's experience

    International Nuclear Information System (INIS)

    Soldermann, R.; Poizat, F.; Sekri, A.; Faydide, B.; Dumas, J.M.

    1997-01-01

    The development of an accelerated version of the advanced CATHARe-1 thermal hydraulics code designed for EDF training simulators (CATHARE-SIMU) was successfully completed as early as 1991. Its successful integration as the principal model of the SIPA Post-Accident Simulator meant that its use could be extended to full-scale simulators as part of the renovation of the stock of existing simulators. In order to further extend the field of application to accidents occurring in shutdown states requiring action and to catch up with developments in respect of the CATHARE code, EDF initiated the SCAR Project designed to adapt CATHARE-2 to simulator requirements (acceleration, parallelization of the computation and extension of the simulation range). In other respects, the installation of SIPA on workstations means that the authors can envisage the application of this remarkable training facility to the understanding of thermal hydraulics accident phenomena

  12. A study on the thermal hydraulics in rod bundles

    International Nuclear Information System (INIS)

    Chung, Moon Ki; Yang, Sun Kyu

    1989-03-01

    In order to improve the thermal hydraulic characteristics of the nuclear reactor core, it is necessary to obtain better understanding of the coolant flow and the enthalpy distribution in complex rod bundle geometries. The purpose of this report is to obtain a comprehensive survey on the thermal hydraulic in rod bundles from both experimental and numerical point of view. From references on experimental study, measurement methods and results of the flow velocity and the pressure drop in the subchannels of rod bundles are expressed. The microscopic flow characteristics of the subchannels and spacer grid effect on the flow structure are described. Physical phenomena and measurement methods of the secondary flow are also described. From references on the numerical study, general numerical methods are expressed. Numerical studies on the laminar flow and turbulent flow such as 1-equation and 2-equation model are reviewed.(Author)

  13. Outage Risk Assessment and Management (ORAM) thermal-hydraulics toolkit

    International Nuclear Information System (INIS)

    Denny, V.E.; Wassel, A.T.; Issacci, F.; Pal Kalra, S.

    2004-01-01

    A PC-based thermal-hydraulic toolkit for use in support of outage optimization, management and risk assessment has been developed. This mechanistic toolkit incorporates simple models of key thermal-hydraulic processes which occur during an outage, such as recovery from or mitigation of outage upsets; this includes heat-up of water pools following loss of shutdown cooling, inadvertent drain down of the RCS, boiloff of coolant inventory, heatup of the uncovered core, and reflux cooling. This paper provides a list of key toolkit elements, briefly describes the technical basis and presents illustrative results for RCS transient behavior during reflux cooling, peak clad temperatures for an uncovered core and RCS response to loss of shutdown cooling. (author)

  14. State of the art of thermal-hydraulics of BWRs

    International Nuclear Information System (INIS)

    Rouhani, Z.

    1980-10-01

    The present report is a summary review of the developments in the field of thermal-hydraulics of Boiling Water Reactors. It covers briefly the development of BWR systems, including some comparison of the main features of the modern BWRs that are marketed by different vendors. The analytical aspects of BWR are also covered briefly with some remarks on the problem areas and limitations in this field. (author)

  15. Application of thermal-hydraulic codes in the nuclear sector

    International Nuclear Information System (INIS)

    Queral, C.; Coriso, M.; Garcia Sedano, P. J.; Ruiz, J. A.; Posada, J. M.; Jimenez Varas, G.; Sol, I.; Herranz, L. E.

    2011-01-01

    Use of thermal-hydraulic codes is extended all over many different aspects of nuclear engineering. This article groups and briefly describes the main features of some of the well known codes as an introduction to their recent applications in the Spain nuclear sector. the broad range and quality of applications highlight the maturity achieved both in industry and research organizations and universities within the Spanish nuclear sector. (Author)

  16. Thermal-hydraulic interfacing code modules for CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Liu, W.S.; Gold, M.; Sills, H. [Ontario Hydro Nuclear, Toronto (Canada)] [and others

    1997-07-01

    The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis.

  17. The analysis of thermal-hydraulic models in MELCOR code

    Energy Technology Data Exchange (ETDEWEB)

    Kim, M H; Hur, C; Kim, D K; Cho, H J [POhang Univ., of Science and TECHnology, Pohang (Korea, Republic of)

    1996-07-15

    The objective of the present work is to verify the prediction and analysis capability of MELCOR code about the progression of severe accidents in light water reactor and also to evaluate appropriateness of thermal-hydraulic models used in MELCOR code. Comparing the results of experiment and calculation with MELCOR code is carried out to achieve the above objective. Specially, the comparison between the CORA-13 experiment and the MELCOR code calculation was performed.

  18. Thermal-hydraulic interfacing code modules for CANDU reactors

    International Nuclear Information System (INIS)

    Liu, W.S.; Gold, M.; Sills, H.

    1997-01-01

    The approach for CANDU reactor safety analysis in Ontario Hydro Nuclear (OHN) and Atomic Energy of Canada Limited (AECL) is presented. Reflecting the unique characteristics of CANDU reactors, the procedure of coupling the thermal-hydraulics, reactor physics and fuel channel/element codes in the safety analysis is described. The experience generated in the Canadian nuclear industry may be useful to other types of reactors in the areas of reactor safety analysis

  19. VHTR core modeling: coupling between neutronic and thermal-hydraulics

    International Nuclear Information System (INIS)

    Limaiem, I.; Damian, F.; Raepsaet, X.; Studer, E.

    2005-01-01

    Following the present interest in the next generation nuclear power plan (NGNP), Cea is deploying special effort to develop new models and qualify its research tools for this next generation reactors core. In this framework, the Very High Temperature Reactor concept (VHTR) has an increasing place in the actual research program. In such type of core, a strong interaction exists between neutronic and thermal-hydraulics. Consequently, the global core modelling requires accounting for the temperature feedback in the neutronic models. The purpose of this paper is to present the new neutronic and thermal-hydraulics coupling model dedicated to the High Temperature Reactors (HTR). The coupling model integrates a new version of the neutronic scheme calculation developed in collaboration between Cea and Framatome-ANP. The neutronic calculations are performed using a specific calculation processes based on the APOLLO2 transport code and CRONOS2 diffusion code which are part of the French reactor physics code system SAPHYR. The thermal-hydraulics model is characterised by an equivalent porous media and 1-D fluid/3-D thermal model implemented in the CAST3M/ARCTURUS code. The porous media approach involves the definition of both homogenous and heterogeneous models to ensure a correct temperature feedback. This study highlights the sensitivity of the coupling system's parameters (radial/axial meshing and data exchange strategy between neutronic and thermal-hydraulics code). The parameters sensitivity study leads to the definition of an optimal coupling system specification for the VHTR. Besides, this work presents the first physical analysis of the VHTR core in steady-state condition. The analysis gives information about the 3-D power peaking and the temperature coefficient. Indeed, it covers different core configurations with different helium distribution in the core bypass. (authors)

  20. Thermal-hydraulic design of the 200 MW NHR

    Energy Technology Data Exchange (ETDEWEB)

    Jincai, Li; Zuying, Gao; Baocheng, Xu; Junxiao, He [Institute of Nuclear Energy and Technology, Tsingua Univ., Beijing (China)

    1997-09-01

    The main problems regarding the AST-500 NHR thermal-hydraulics are considered. Basic thermal data of the reactor plant are given and peculiarities of coolant parameters at natural convection in the primary circuit are discussed. The in-reactor instrumentation system is briefly describes, as well as the results of natural-convective flow characteristics investigations using reactor test models. (author). 4 refs, 5 figs.

  1. CFD studies on thermal hydraulics of spallation targets

    International Nuclear Information System (INIS)

    Tak, N.I.; Batta, A.; Cheng, X.

    2005-01-01

    Full text of publication follows: Due to the fast advances in computer hardware as well as software in recent years, more and more interests have been aroused to use computational fluid dynamics (CFD) technology in nuclear engineering and designs. During recent many years, Forschungszentrum Karlsruhe (FZK) has been actively involved in the thermal hydraulic analysis and design of spallation targets. To understand the thermal hydraulic behaviors of spallation targets very detailed simulations are necessary because of their complex geometries, complicated boundary conditions such as spallation heat distributions, and very strict design limits. A CFD simulation is believed to be the best for this purpose even though the validation of CFD codes are not perfectly completed yet in specific topics like liquid metal heat transfer. The research activities on three spallation targets (i.e., MEGAPIE, TRADE, and XADS targets) are currently very active in Europe in order to consolidate the European ADS road-map. In the thermal hydraulics point of view, two kinds of the research activities, i.e., (1) numerical design and (2) experimental work, are required to achieve the objectives of these targets. It should be noted that CFD studies play important role on both kinds of two activities. A preliminary design of a target can be achieved by sophisticated CFD analysis and pre-and-post analyses of an experimental work using a CFD code help the design of the test section of the experiment as well as the analysis of the experimental results. The present paper gives an overview about the recent CFD studies relating to thermal hydraulics of the spallation targets recently involved in FZK. It covers numerical design studies as well as CFD studies to support experimental works. The CFX code has been adopted for the studies. Main recent results for the selected examples performed by FZK are presented and discussed with their specific lessons learned. (authors)

  2. Thermal-hydraulic characteristics of double flat core HCLWR

    International Nuclear Information System (INIS)

    Sugimoto, Jun; Iwamura, Takamichi; Okubo, Tsutomu; Murao, Yoshio

    1989-02-01

    A thermal-hydraulic characteristics of double flat core high conversion light water reactor (HCLWR) is described. The concept of flat core proposed by Ishiguro et al. is to achieve negative void reactivity coefficient in tight lattice core, and at the same time, high conversion ratio and high burnup can be obtainable. The proposed double flat core HCLWR, based on these physical advantages and the consideration of safety assurance, aims at efficient use of the pressure vessel space to produce comparable thermal output as current 3-loop PWRs. The present work revealed the following items concerning the thermalhydraulic feasibility of the double flat core HCLWR: (1) Main thermal-hydraulic parameters of the plant can be almost the same as current PWRs, showing the use of PWR standard components without major modifications except in core region. (2) Heat removal from the fuel rod in a steady operational condition has enough margin to the critical heat flux (CHF) limit, which is evaluated with the existing CHF correlations. (3) The calculation by REFLA code shows that the maximum cladding temperature in LOCA-reflood is estimated to be far lower than the licensing criteria. It is therefore considered that the proposed double flat core HCLWR is feasible from the point of thermal-hydraulics. Since the available data base has certain applicational limit to the very short core as the present double flat core HCLWR, further detailed assessment is required. (author)

  3. Thermal-Hydraulic Performance of Scrubbing Nozzle Used for CFVS

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyun Chul; Lee, Doo Yong; Jung, Woo Young; Lee, Jong Chan; Kim, Gyu Tae [FNC TECH, Yongin (Korea, Republic of)

    2016-05-15

    A Containment Filtered Venting System (CFVS) is the most interested device to mitigate a threat against containment integrity under the severe accident of nuclear power plant by venting with the filtration of the fission products. FNC technology and partners have been developed the self-priming scrubbing nozzle used for the CFVS which is based on the venturi effect. The thermal-hydraulic performances such as passive scrubbing water suction as well as pressure drop across the nozzle have been tested under various thermal-hydraulic conditions. The two types of test section have been built for testing the thermal-hydraulic performance of the self-priming scrubbing nozzle. Through the visualization loop, the liquid suction performance through the slit, pressure drop across the nozzle are measured. The passive water suction flow through the suction slit at the throat is important parameter to define the scrubbing performance of the self-priming scrubbing nozzle. The water suction flow is increased with the increase of the overhead water level at the same inlet gas flow. It is not so much changed with the change of inlet gas flow at the overhead water level.

  4. Views on the future of thermal hydraulic modeling

    Energy Technology Data Exchange (ETDEWEB)

    Ishii, M. [Purdue Univ., West Lafayette, IN (United States)

    1997-07-01

    It is essential for the U.S. NRC to sustain the highest level of the thermal-hydraulics and reactor safety research expertise and continuously improve their accident analysis capability. Such expertise should span over four different areas which are strongly related to each other. These are: (1) Reactor Safety Code Development, (2) Two-phase Flow Modeling, (3) Instrumentation and Fundamental Experimental Research, and (4) Separate Effect and Integral Test. The NRC is already considering a new effort in the area of advanced thermal-hydraulics effort. Its success largely depends on the availability of a significantly improved two-phase flow formulation and constitutive relations supported by detailed experimental data. Therefore, it is recommended that the NRC start significant research efforts in the areas of two-phase flow modeling, instrumentation, basic and separate effect experiments which should be pursued systematically and with clearly defined objectives. It is desirable that some international program is developed in this area. This paper is concentrated on those items in the thermal-hydraulic area which eventually determine the quality of future accident analysis codes.

  5. Thermal hydraulic feasibility assessment for the Spent Nuclear Fuel Project

    International Nuclear Information System (INIS)

    Heard, F.J.; Cramer, E.R.; Beaver, T.R.; Thurgood, M.J.

    1996-01-01

    A series of scoping analyses have been completed investigating the thermal-hydraulic performance and feasibility of the Spent Nuclear Fuel Project (SNFP) Integrated Process Strategy (IPS). The SNFP was established to develop engineered solutions for the expedited removal, stabilization, and storage of spent nuclear fuel from the K Basins at the U.S. Department of Energy's Hanford Site in Richland, Washington. The subject efforts focused on independently investigating, quantifying, and establishing the governing heat production and removal mechanisms for each of the IPS operations and configurations, obtaining preliminary results for comparison with and verification of other analyses, and providing technology-based recommendations for consideration and incorporation into the design bases for the SNFP. The goal was to develop a series fo thermal-hydraulic models that could respond to all process and safety-related issues that may arise pertaining to the SNFP. A series of sensitivity analyses were also performed to help identify those parameters that have the greatest impact on energy transfer and hence, temperature control. It is anticipated that the subject thermal-hydraulic models will form the basis for a series of advanced and more detailed models that will more accurately reflect the thermal performance of the IPS and alleviate the necessity for some of the more conservative assumptions and oversimplifications, as well as form the basis for the final process and safety analyses

  6. Thermal-Hydraulic Tests for Reactor Core Safety

    International Nuclear Information System (INIS)

    Chun, Se Young; Chung, Moon Ki; Baek, Won Pil and others

    2005-04-01

    The reflood experiments for single rod annulus geometry have been performed to investigate the effect of spacer grid on thermal-hydraulics under reflood conditions. The reflood experimental loop for 6x6 rod bundle with a spacer grid developed in Korea has been provided. About 8000 data points for Post-CHF heat transfer have been obtained from the experiments About 1400 CHF data points for 3x3 Water and 5x5 Freon rod bundles have been obtained. The existing evaluation methodology for core safety under return-to-power conditions has been investigated using KAERI low flow CHF database. The hydraulic tests for turbulence mixing characteristics in subchannel of 5x5 rod bundle have been carried out using advanced measurement technique, LVD and the database for various spacer grids have been provided. In order to measure the turbulence mixing characteristics in details, the hydraulic loop with a magnified 5x5 rod bundle has been prepared. The database which was constructed through a systematic thermal hydraulic tests for the reflood phenomenon, CHF, Post-CHF is surely to be useful to the industry field, the regulation body and the development of thermal-hydraulic analysis code

  7. Views on the future of thermal hydraulic modeling

    International Nuclear Information System (INIS)

    Ishii, M.

    1997-01-01

    It is essential for the U.S. NRC to sustain the highest level of the thermal-hydraulics and reactor safety research expertise and continuously improve their accident analysis capability. Such expertise should span over four different areas which are strongly related to each other. These are: (1) Reactor Safety Code Development, (2) Two-phase Flow Modeling, (3) Instrumentation and Fundamental Experimental Research, and (4) Separate Effect and Integral Test. The NRC is already considering a new effort in the area of advanced thermal-hydraulics effort. Its success largely depends on the availability of a significantly improved two-phase flow formulation and constitutive relations supported by detailed experimental data. Therefore, it is recommended that the NRC start significant research efforts in the areas of two-phase flow modeling, instrumentation, basic and separate effect experiments which should be pursued systematically and with clearly defined objectives. It is desirable that some international program is developed in this area. This paper is concentrated on those items in the thermal-hydraulic area which eventually determine the quality of future accident analysis codes

  8. Primary system thermal hydraulics of future Indian fast reactors

    Energy Technology Data Exchange (ETDEWEB)

    Velusamy, K., E-mail: kvelu@igcar.gov.in [Thermal Hydraulics Section, Indira Gandhi Centre for Atomic Research, Kalpakkam 603102 (India); Natesan, K.; Maity, Ram Kumar; Asokkumar, M.; Baskar, R. Arul; Rajendrakumar, M.; Sarathy, U. Partha; Selvaraj, P.; Chellapandi, P. [Thermal Hydraulics Section, Indira Gandhi Centre for Atomic Research, Kalpakkam 603102 (India); Kumar, G. Senthil; Jebaraj, C. [AU-FRG Centre for CAD/CAM, Anna University, Chennai 600 025 (India)

    2015-12-01

    Highlights: • We present innovative design options proposed for future Indian fast reactor. • These options have been validated by extensive CFD simulations. • Hotspot factors in fuel subassembly are predicted by parallel CFD simulations. • Significant safety improvement in the thermal hydraulic design is quantified. - Abstract: As a follow-up to PFBR (Indian prototype fast breeder reactor), many FBRs of 500 MWe capacity are planned. The focus of these future FBRs is improved economy and enhanced safety. They are envisaged to have a twin-unit concept. Design and construction experiences gained from PFBR project have provided motivation to achieve an optimized design for future FBRs with significant design changes for many critical components. Some of the design changes include, (i) provision of four primary pipes per primary sodium pump, (ii) inner vessel with single torus lower part, (iii) dome shape roof slab supported on reactor vault, (iv) machined thick plate rotating plugs, (v) reduced main vessel diameter with narrow-gap cooling baffles and (vi) safety vessel integrated with reactor vault. This paper covers thermal hydraulic design validation of the chosen options with respect to hot and cold pool thermal hydraulics, flow requirement for main vessel cooling, inner vessel temperature distribution, safety analysis of primary pipe rupture event, adequacy of decay heat removal capacity by natural convection cooling, cold pool transient thermal loads and thermal management of top shield and reactor vault.

  9. Institutional disposition and management of end-of-life electronics.

    Science.gov (United States)

    Babbitt, Callie W; Williams, Eric; Kahhat, Ramzy

    2011-06-15

    Institutions both public and private face a challenge to develop policies to manage purchase, use, and disposal of electronics. Environmental considerations play an increasing role in addition to traditional factors of cost, performance and security. Characterizing current disposition practices for end-of-life electronics is a key step in developing policies that prevent negative environmental and health impacts while maximizing potential for positive social and economic benefits though reuse. To provide a baseline, we develop the first characterization of quantity, value, disposition, and flows of end-of-life electronics at a major U.S. educational institution. Results of the empirical study indicate that most end-of-first-life electronics were resold through public auction to individuals and small companies who refurbish working equipment for resale or sell unusable products for reclamation of scrap metal. Desktop and laptop computers sold for refurbishing and resale averaged U.S. $20-100 per unit, with computers sold directly to individuals for reuse reaching $250-350 per unit. This detailed assessment was coupled with a benchmarking survey of end-of-life electronics management practices at other U.S. universities. Survey results indicate that while auctions are still commonplace, an increasing number of institutions are responding to environmental concerns by creating partnerships with local recycling and resale entities and mandating domestic recycling. We use the analyses of current disposition practices as input to discuss institutional strategies for managing electronics. One key issue is the tension between benefits of used equipment sales, in terms of income for the institution and increased reuse for society, and the environmental risks because of unknown downstream practices.

  10. Environmental assessment of end-of-life textiles in Denmark

    DEFF Research Database (Denmark)

    Koligkioni, Athina; Parajuly, Keshav; Sørensen, Birgitte Lilholt

    2018-01-01

    The European Union is on its way to a circular economy through eco-design, waste prevention, reuse and recycling of products and materials. This study analyzes the environmental effects of end-of-life textile management in Denmark. First, a Mass Flow Analysis was performed for textile flows from...... sales to consumers to end processes, which revealed that absolute consumption has grown significantly over the last years. Data on generation and management of used textiles indicated that around 40% are discarded with residual waste, another 40% are captured by collection for reuse channels, and around...

  11. GPs and end of life decisions : views and experiences

    OpenAIRE

    Abela, Jurgen

    2015-01-01

    The views and experiences of GPs with respect to end of life (EoL) care are seldom addressed. The aim of this article is to better understand this aspect of care. A cross-sectional survey of all doctors in the country was designed and set up. The overall response was 396 (39.7%), 160 of which were GPs. 28.7% of GPs received no formal training in palliative medicine. 89.8% of respondents declared that their religion was important in EoL care. 45.3% agreed with the right of a patient to decide ...

  12. PHENIX Fast TOF

    Energy Technology Data Exchange (ETDEWEB)

    Soha, Aria [Fermi National Accelerator Lab. (FNAL), Batavia, IL (United States); Chiu, Mickey [Brookhaven National Lab. (BNL), Upton, NY (United States); Mannel, Eric [Brookhaven National Lab. (BNL), Upton, NY (United States); Stoll, Sean [Brookhaven National Lab. (BNL), Upton, NY (United States); Lynch, Don [Brookhaven National Lab. (BNL), Upton, NY (United States); Boose, Steve [Brookhaven National Lab. (BNL), Upton, NY (United States); Northacker, Dave [Brookhaven National Lab. (BNL), Upton, NY (United States); Alfred, Marcus [Howard Univ., Washington, DC (United States); Lindesay, James [Howard Univ., Washington, DC (United States); Chujo, Tatsuya [Univ. of Tsukuba (Japan); Inaba, Motoi [Univ. of Tsukuba (Japan); Nonaka, Toshihiro [Univ. of Tsukuba (Japan); Sato, Wataru [Univ. of Tsukuba (Japan); Sakatani, Ikumi [Univ. of Tsukuba (Japan); Hirano, Masahiro [Univ. of Tsukuba (Japan); Choi, Ihnjea [Univ. of Illinois, Urbana-Champaign, IL (United States)

    2014-01-15

    This is a technical scope of work (TSW) between the Fermi National Accelerator Laboratory (Fermilab) and the experimenters of PHENIX Fast TOF group who have committed to participate in beam tests to be carried out during the FY2014 Fermilab Test Beam Facility program. The goals for this test beam experiment are to verify the timing performance of the two types of time-of-flight detector prototypes.

  13. End-of-life issues as perceived by Lebanese judges.

    Science.gov (United States)

    Adib, Salim M; Kawas, Sami H; Hajjar, Theresa A

    2003-05-01

    to assess the attitudes of judges in Beirut, Lebanon, regarding end-of-life issues such as assisted suicide and withholding or withdrawing life-sustaining treatment. 85% of all currently acting and in-training judges and public prosecutors in Beirut (N=135) were surveyed using a mailed questionnaire that assessed attitudes toward intervention in five hypothetical cases. The associations of attitudes, on a scale from least to most 'sympathetic' toward assisting those who desire to end their lives, were measured by a variety of personal, social and professional variables. younger individuals, and those who have not yet been formally appointed as judges, were significantly more sympathetic to withdrawal or withholding of life-sustaining devices when patients or their proxies requested it, and more in support of assisted suicide. Gender, religious denomination, religious practice, and personal experience with prolonged illness leading to death among close friends or family, were generally not significant predictors of respondents' attitudes. Years of experience as a judge correlated strongly with age and may have contributed to its predictive effect. a relatively more sympathetic attitude among younger judges, many of them women, and among trainees, may reflect a historical evolution in younger age-groups in Lebanon today. A survey of opinions in the public may help reach a more conclusive understanding in this regard. In any case, judges in Lebanon will remain important partners in the debate, as they will continue to be the final interpreters of the letter of the law in end-of-life issues.

  14. End-of-Life Decisions and Advanced Old Age

    Directory of Open Access Journals (Sweden)

    Stoyles

    2014-07-01

    Full Text Available Despite the fact that most people die in advanced old age, little attention is given to cases involving older people in debates about the moral and legal dimensions of end-of-life decision making. The purpose of this paper is to establish some of the ways our discussions should change as we pay attention to important factors influencing end-of-life decisions for people in advanced old age. Focusing on the prevalence of comorbidities and the likelihood that people in advanced old age will experience an extended period of declining function before death, I argue that our debates should be expanded to include greater consideration of how we want to live in the final stages of life. With this, I am arguing against the tendency to think that “end-of-life” decision making concerns only making decisions about when and how it is appropriate to terminate a person’s life. I argue, further, that we should move away from the medicalization of dying.

  15. [End of life decisions, the Dutch form through Spanish eyes].

    Science.gov (United States)

    Belloc Rocasalbas, M; Girbes, A R J

    2011-03-01

    Abroad, but also in The Netherlands, there are many misunderstandings concerning end of life decisions and euthanasia. In general, euthanasia does not play any role in the intensive care units, simply because it does not fulfill the conditions to carry it out. However, there is still confusion, merely due to the assumption that the Dutch situation is different because of their legislation on euthanasia. The use of the unclear terminology such as "passive euthanasia", "voluntary euthanasia" or "involuntary euthanasia" contributes to the confusion of lay people and physicians, and should therefore be avoided. End of life decisions in intensive care patients are in fact a structural part of work of intensivists. Collecting all necessary information including the wishes and will of the patient, medical expertise and acknowledging limitations of medical treatment will help to determine futility of treatment goals. Once it is determined that surviving the intensive care unit with a quality of life acceptable for the patient is beyond reach, the goal of treatment should be improved and the dying process optimized. Stopping a treatment modality at the request of a will-competent patient or because of futility is not euthanasia. Copyright © 2010 Elsevier España, S.L. y SEMICYUC. All rights reserved.

  16. Balancing dual roles in end-of-life research.

    Science.gov (United States)

    Martin, Wanda; Grey, Meredith; Webber, Terry; Robinson, Linnea; Hartt, Nancy; Cairns, Moira; Stajduhar, Kelli

    2007-01-01

    Ethical and practical issues are sure to arise from the majority of research studies done with palliative populations. Whether it is feeling opportunistic, being emotionally available, or struggling with witnessing a gap in service and needs of the participants receiving care, nurses involved in research find a way to balance both roles to meet the needs of the participants as well as the study (McIlfatrick, Sullivan, & McKenna, 2006). This paper highlights some of the practical and ethical issues that arise when frontline nurses also take on the role of research assistant for studies with palliative populations. Specifically, the authors highlight their personal experiences based on their research assistant work on a study examining family caregiver coping in end-of-life cancer care. The authors discuss the "balancing act" of taking on these dual roles and offer recommendations on how to be with and approach people when doing research at the end of life using a framework based on Swanson's Theory of Caring (1991).

  17. [Vulnerations of Human Dignity At The End of Life].

    Science.gov (United States)

    Germán Zurriaráin, Roberto

    2017-01-01

    Death is constitutive of human nature and therefore it must happen naturally. But there are mainly two ways that falsify it: euthanasia and therapeutic obstinacy. Two wrong choices that do not accept the human reality of death (the first, anticipates death and the second, delays it). From the philosophical and ethical point of view, both options are rejected, because they are against human dignity at the end of life. Aside from these, this article also rejects the different names which are given to refer to euthanasia, that also go against human nature at the end of life. On the other hand, do not confuse euthanasia with sedation. Both have a common goal to prevent the patient from feeling pain and suffering. To achieve this goal, both options administer ″drugs″ to the patient. But in the administration of drugs in euthanasia involves ending patient's life. The administration of drugs in sedation aims for the patient's death to occur naturally. Finally, we briefly discuss the basic care necessary in these situations. The absence of basic care cannot become a covert euthanasia. The patient must die from his/her illness, never from a lack of care. All human actions (euthanasia, sedation, therapeutic obstinacy and basic care) should be an expression and manifestation of what human dignity demands. Such dignity is expressed in the actions performed by human beings.

  18. End-of-life palliative chemotherapy: Where do we stand?

    International Nuclear Information System (INIS)

    Mohammed, A.A.; Al-Zahrani, A.S.; Ghanem, H.M.; El Saify, A.M.; EL-Khatib, H.M.; Mohammed, A.A.; Farooq, M.U.

    2015-01-01

    Background: This study evaluates the use of palliative chemotherapy (PCT) and possible associated factors at the end of life. Method: The study includes all advanced non hematological cancer patients who died in the King Abdullah Medical City during the period from January 2011 to April 2014. Demographic and disease features were registered. Results: 420 patients were included in the study, median age 62 years (range 17-108); 52% female and 48% male. 87.4% of patients were Saudis and 12.6% non Saudis. 124 (29.5%) patients received PCT at the last month before death (LM-PCT): 21.8%, 22.6% and 55.6% within one, two and four weeks of death, respectively. Place of death (critical care vs. regular ward) and mode of admission (ER vs. OPD vs. Transferred) had a strong association with LM-PCT (p< 0.0001, / = 0.35) and (p< 0.0001, V = 0.43), respectively. There was a gradual increase in the number of patients receiving LM-PCT from January 2011 to April 2014; 15.3%, 28.2%, 37.1% and 19.4%, respectively. Conclusion: In our center; at the end of life, there is a gradual increase in the number of patients receiving chemotherapy which significantly increased cancer patients’ odds without clear predictive factors associated with its use, which calls into question the benefits of PCT in terminally ill cancer patients.

  19. Labelling of end-of-life decisions by physicians.

    Science.gov (United States)

    Deyaert, Jef; Chambaere, Kenneth; Cohen, Joachim; Roelands, Marc; Deliens, Luc

    2014-07-01

    Potentially life-shortening medical end-of-life practices (end-of-life decisions (ELDs)) remain subject to conceptual vagueness. This study evaluates how physicians label these practices by examining which of their own practices (described according to the precise act, the intention, the presence of an explicit patient request and the self-estimated degree of life shortening)they label as euthanasia or sedation. We conducted a large stratified random sample of death certificates from 2007 (N=6927).The physicians named on the death certificate were approached by means of a postal questionnaire asking about ELDs made in each case and asked to choose the most appropriate label to describe the ELD. Response rate was 58.4%. In the vast majority of practices labelled as euthanasia, the self-reported actions of the physicians corresponded with the definition in the Belgian euthanasia legislation; practices labelled as palliative or terminal sedation lack clear correspondence with definitions of sedation as presented in existing guidelines. In these cases, an explicit life-shortening intention by means of drug administration was present in 21.6%, life shortening was estimated at more than 24 h in 51% and an explicit patient request was absentin 79.7%. Our results suggest that, unlike euthanasia,the concept of palliative or terminal sedation covers abroad range of practices in the minds of physicians. This ambiguity can be a barrier to appropriate sedation practice and indicates a need for better knowledge of the practice of palliative sedation by physicians.

  20. BEPU-FSAR: establishing a background for extension of nuclear thermal hydraulic principles to non thermal-hydraulic codes

    Energy Technology Data Exchange (ETDEWEB)

    Menzel, Francine; Sabundjian, Gaianê, E-mail: franmenzel@gmail.com, E-mail: gdjian@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil); D’Auria, Francesco, E-mail: f.dauria@ing.unipi.it [University of Pisa, San Piero a Grado Nuclear Research Group (Italy)

    2017-07-01

    Nuclear thermal hydraulic and accident analysis are based in three pillar activities, which consists in: Scaling, Coupling and V and V. Each of them are established technology, with key documents to describe and widely used. The final goal of this work is to apply the BEPU methodology in all parts of FSAR where analytical techniques are needed (BEPU-FSAR) and for that the crucial step is the transfer of the BEPU concepts into the other areas. In this sense, the issue is how to adapt to other disciplines the pillar activities presented in the thermal hydraulic area. For that we need to identify which elements can be applied in the other areas, to show that the proposed methodology is feasible. This work aims to discuss the first steps towards a BEPU-FSAR methodology and to show that the Scaling, Coupling and V and V elements, currently done for thermal-hydraulic codes, can be also done for different codes, which are used to perform different analysis included on a FSAR of a generic plant. (author)

  1. Development of realistic thermal-hydraulic system analysis codes ; development of thermal hydraulic test requirements for multidimensional flow modeling

    Energy Technology Data Exchange (ETDEWEB)

    Suh, Kune Yull; Yoon, Sang Hyuk; Noh, Sang Woo; Lee, Il Suk [Seoul National University, Seoul (Korea)

    2002-03-01

    This study is concerned with developing a multidimensional flow model required for the system analysis code MARS to more mechanistically simulate a variety of thermal hydraulic phenomena in the nuclear stem supply system. The capability of the MARS code as a thermal hydraulic analysis tool for optimized system design can be expanded by improving the current calculational methods and adding new models. In this study the relevant literature was surveyed on the multidimensional flow models that may potentially be applied to the multidimensional analysis code. Research items were critically reviewed and suggested to better predict the multidimensional thermal hydraulic behavior and to identify test requirements. A small-scale preliminary test was performed in the downcomer formed by two vertical plates to analyze multidimensional flow pattern in a simple geometry. The experimental result may be applied to the code for analysis of the fluid impingement to the reactor downcomer wall. Also, data were collected to find out the controlling parameters for the one-dimensional and multidimensional flow behavior. 22 refs., 40 figs., 7 tabs. (Author)

  2. Leak detection in Phenix and Super Phenix steam generators

    Energy Technology Data Exchange (ETDEWEB)

    Cambillard, E [Centre d' Etudes Nucleaires de Saclay, Gif-sur-Yvette (France)

    1978-10-01

    Water leak detection Phenix and Super Phenix steam generators is based on measurement of the hydrogen produced by the reaction of sodium with water. The hydrogen evolves in the sodium in which the steam generator tubes are completely immersed. Depending on service conditions, however (sodium temperature and flow velocity), the hydrogen may appear in the argon existing above the free levels. This is why, although the Phenix steam generators do not feature free levels, measurement systems were added to measure the hydrogen concentration in the argon in the expansion tanks. Super Phenix steam generators are fitted at their outlet with systems for measuring hydrogen in the sodium, and above their free level with a system for measuring hydrogen in the argon. The measurement systems have nickel tube probes connected to circuits kept under vacuum by an ion pump. The hydrogen partial pressure is measured by a mass spectrometer. Super Phenix measurement systems differ from Phenix systems essentially in the temperature regulation of the sodium reaching the nickel tube probes, and in the centralization of the supply and measurement systems of the ion pumps and mass spectrometers. This paper deals with description, calibration and operating conditions of the hydrogen detection systems in sodium and argon in Phenix and Super Phenix steam generators. (author)

  3. The PHENIX experimental irradiation program

    International Nuclear Information System (INIS)

    Michel, P.; Courcon, P.; Coulon, P.

    1985-03-01

    The PHENIX experimental irradiation program represents a substancial volume of work. For example, more than forty experiments were in the core during the 33rd PHENIX irradiation cycle at the end of 1984. This program ensures the implementation, optimization and qualification of new solutions for the future developpment of French LMFBRs in three significant areas: fissile, fertile and absorber elements

  4. [End-of-Life Care in Intensive Care Units: Nursing strategies of family involvement at the end of life].

    Science.gov (United States)

    Cyrol, Katharina; Fröhlich, Martin R; Piatti, Francesca; Imhof, Lorenz

    2018-06-01

    Background: Family members of people dying in the intensive care unit (ICU) are exposed to many stress factors and they often do not experience involvement in End-of-Life (EoL) situations. For example, they criticize a low degree of participation in patients care, delayed or incomplete information and lack of privacy. Even nursing staff is facing various obstacles in EoL situations in ICUs. Aim: This study investigates strategies used by ICU nursing staff in German-speaking Switzerland to increase family members participation in situations at the end of life. Method: Data was collected by conducting 12 semi-structured interviews using an approach based on Grounded Theory. A model was developed to explain nursing strategies for family involvement in EoL situations in the ICU. Conclusions: Nurses provide personal space and tranquillity for family members and allow them to be present at any time. Against this background, they support family members and enable them to say goodbye consciously to a loved one. Subsequent work should examine the effectiveness of the strategies described, particularly in terms of stress reactions displayed by family members in the aftermath of EoL situations. In practice, family members should be provided space for privacy. The entire healthcare team is recommended to identify and pursue common values and objectives. Moreover, intradisciplinary exchange and mentoring need to be encouraged. In order to prepare future nursing staff for EoL situations in the ICU, recognizing and promoting their educational skills is mandatory.

  5. Spirituality in cancer care at the end of life.

    Science.gov (United States)

    Ferrell, Betty; Otis-Green, Shirley; Economou, Denice

    2013-01-01

    There is a compelling need to integrate spirituality into the provision of quality palliative care by oncology professionals. Patients and families report the importance of spiritual, existential, and religious concerns throughout the cancer trajectory. Leading palliative care organizations have developed guidelines that define spiritual care and offer recommendations to guide the delivery of spiritual services. There is growing recognition that all team members require the skills to provide generalist spiritual support. Attention to person-centered, family-focused oncology care requires the development of a health care environment that is prepared to support the religious, spiritual, and cultural practices preferred by patients and their families. These existential concerns become especially critical at end of life and following the death for family survivors. Oncology professionals require education to prepare them to appropriately screen, assess, refer, and/or intervene for spiritual distress.

  6. End-of-life resource recovery from emerging electronic products

    DEFF Research Database (Denmark)

    Parajuly, Keshav; Habib, Komal; Cimpan, Ciprian

    2016-01-01

    Integrating product design with appropriate end-of-life (EoL) processing is widely recognized to have huge potentials in improving resource recovery from electronic products. In this study, we investigate both the product characteristics and EoL processing of robotic vacuum cleaner (RVC), as a case...... of emerging electronic product, in order to understand the recovery fate of different materials and its linkage to product design. Ten different brands of RVC were dismantled and their material composition and design profiles were studied. Another 125 RVCs (349 kg) were used for an experimental trial...... at a conventional ‘shred-and-separate’ type preprocessing plant in Denmark. A detailed material flow analysis was performed throughout the recycling chain. The results show a mismatch between product design and EoL processing, and the lack of practical implementation of ‘Design for EoL’ thinking. In the best...

  7. Examining End-of-Life Case Management: Systematic Review

    Directory of Open Access Journals (Sweden)

    Roger E. Thomas

    2014-01-01

    Full Text Available Case management was initiated in the 1970s to reduce care discontinuity. A literature review focused on end-of-life (EOL case management identified 17 research articles, with content analysis revealing two themes: (a seeking to determine or establish the value of EOL case management and (b identifying ways to improve EOL case management. The evidence, although limited, suggests that EOL case management is helpful to dying individuals and their families. Research is needed to more clearly illustrate its usefulness or outcomes and the extent of need for it and actual availability. Among other benefits, EOL case management may help reduce hospital utilization, a major concern with the high cost of hospital-based care and the increased desire for home-based EOL care.

  8. International Space Station End-of-Life Probabilistic Risk Assessment

    Science.gov (United States)

    Duncan, Gary W.

    2014-01-01

    The International Space Station (ISS) end-of-life (EOL) cycle is currently scheduled for 2020, although there are ongoing efforts to extend ISS life cycle through 2028. The EOL for the ISS will require deorbiting the ISS. This will be the largest manmade object ever to be de-orbited therefore safely deorbiting the station will be a very complex problem. This process is being planned by NASA and its international partners. Numerous factors will need to be considered to accomplish this such as target corridors, orbits, altitude, drag, maneuvering capabilities etc. The ISS EOL Probabilistic Risk Assessment (PRA) will play a part in this process by estimating the reliability of the hardware supplying the maneuvering capabilities. The PRA will model the probability of failure of the systems supplying and controlling the thrust needed to aid in the de-orbit maneuvering.

  9. Satellite end of life constraints: Technical and organisational solutions

    Science.gov (United States)

    Cabrières, Bernard; Alby, Fernand; Cazaux, Christian

    2012-04-01

    Since 1974 with the radiocommunication satellite Symphony1, CNES launched and operated 11 GEO and 20 LEO satellites. During those 36 years, both flight segment and ground segment dramatically evolved and operational organisations and techniques equally improved. At the present time, CNES operates 1 GEO satellite and 17 LEO satellites with not much more people and costs than in 1986 when its first Satellite Operation Direction in Toulouse was only in charge of Telecom1A, Telecom1B and Spot1. This fantastic technical evolution combined with the huge increase of services to citizens and governments given by Space systems was unfortunately also associated with an enormous growth of space pollution by debris of all sizes. From the beginning, CNES was a major actor of the international effort to promote regulations in order to try to reduce or at least control this problematic situation. Internally, CNES, not only set up an operational on-call service to deal with collision risks, but decided to do its best to apply the new guidelines to the end of life of satellites under its responsibility even for those developed and launched a very long time ago. For instance, that was the case in 2009 for the reorbitation of the GEO satellite Telecom 2C (launched in 1995) and for the deorbitation of the LEO satellite Spot2 (launched in 1990). In addition, CNES prepares procedures to be able to be as exemplary as possible for its other spacecrafts whose end of life approaches. The constraints and challenges to face in order to cope with these new requirements are multiple: choice of final orbit, realistic calculation of re-entry duration, estimation of residual propellant, electric passivation, management of explosion risks… All these studies and operational experience gained will be helpful for the new role of CNES, which recently became in charge of controlling space operators in the frame of the new French space law on space operations.

  10. Use of opioids and sedatives at End-of-Life

    Directory of Open Access Journals (Sweden)

    Shin Wei Sim

    2014-01-01

    Full Text Available Despite their proven efficacy and safety, opioid and sedative use for palliation in patients afflicted with cancer in Singapore have been shown to be a fraction of that in other countries. This paper explores the various psychosocial and system-related factors that appear to propagate this conservative approach to care in what is largely a western-influenced care practice. A search for publications relating to sedative and opioid usage in Asia was performed on PubMed, Google, Google Scholar, World Health Organization, and Singapore′s government agency websites using search terms such as "opioids," "sedatives," "palliation," "end-of-life-care," "pain management," "palliative care," "cancer pain," "Asia," "Singapore," and "morphine." Findings were classified into three broad groups - system-related, physician-related, and patient-related factors. A cautious medico-legal climate, shortage of physicians trained in palliative care, and lack of instruments for symptom assessment of patients at the end of life contribute to system-related barriers. Physician-related barriers include delayed access to palliative care due to late referrals, knowledge deficits in non-palliative medicine physicians, and sub-optimal care provided by palliative physicians. Patients′ under-reporting of symptoms and fear of addiction, tolerance, and side effects of opioids and sedatives may lead to conservative opioid use in palliative care as well. System-related, physician-related, and patient-related factors play crucial roles in steering the management of palliative patients. Addressing and increasing the awareness of these factors may help ensure patients receive adequate relief and control of distressing symptoms.

  11. Eliciting regret improves decision making at the end of life.

    Science.gov (United States)

    Djulbegovic, Benjamin; Tsalatsanis, Athanasios; Mhaskar, Rahul; Hozo, Iztok; Miladinovic, Branko; Tuch, Howard

    2016-11-01

    Management choices at the end of life are high-stake decisions fraught with emotions, chief among is regret. Our objective in this paper is to test the utility of a regret-based model to facilitate referral to hospice care while helping patients clarify their preferences on how they wish to spend the remaining days of their lives. A prospective cohort study that enrolled consecutive adult patients (n = 178) aware of the terminal nature of their disease. The patients were at the point in care where they had to decide between continuing potentially 'curative/life-prolonging' treatment (Rx) versus hospice care. Preferences were elicited using a Dual Visual Analog Scale regarding the level of regret of omission versus commission (RgO/RgC) towards hospice care and Rx. Each patient's RgO/RgC was contrasted against the predictive probability of death to suggest a management plan, which was then compared with the patient's actual choice. The probability of death was estimated using validated Palliative Performance Scale predictive model. Eighty-five percent (151/178) of patients agreed with the model's recommendations (p < 0.000001). Model predicted the actual choices for 72% (128/178) of patients (p < 0.00001). Logistic regression analysis showed that people who were initially inclined to be referred to hospice and were predicted to choose hospice over disease-directed treatment by the regret model have close to 98% probability of choosing hospice care at the end of their lives. No other factors (age, gender, race, educational status and pain level) affected their choice. Using regret to elicit choices in the end-of-life setting is both descriptively and prescriptively valid. People with terminal disease who are initially inclined to choose hospice and do not regret such a choice will select hospice care with high level of certainty. Copyright © 2016 The Author(s). Published by Elsevier Ltd.. All rights reserved.

  12. Occupational Variation in End-of-Life Care Intensity.

    Science.gov (United States)

    Hyder, Joseph A; Haring, R Sterling; Sturgeon, Daniel; Gazarian, Priscilla K; Jiang, Wei; Cooper, Zara; Lipsitz, Stuart R; Prigerson, Holly G; Weissman, Joel S

    2018-03-01

    End-of-life (EOL) care intensity is known to vary by secular and geographic patterns. US physicians receive less aggressive EOL care than the general population, presumably the result of preferences shaped by work-place experience with EOL care. We investigated occupation as a source of variation in EOL care intensity. Across 4 states, we identified 660 599, nonhealth maintenance organization Medicare beneficiaries aged ≥66 years who died between 2004 and 2011. Linking death certificates, we identified beneficiaries with prespecified occupations: nurses, farmers, clergy, mortuary workers, homemakers, first-responders, veterinary workers, teachers, accountants, and the general population. End-of-life care intensity over the last 6 months of life was assessed using 5 validated measures: (1) Medicare expenditures, rates of (2) hospice, (3) surgery, (4) intensive care, and (5) in-hospital death. Occupation was a source of large variation in EOL care intensity across all measures, before and after adjustment for sex, education, age-adjusted Charlson Comorbidity Index, race/ethnicity, and hospital referral region. For example, absolute and relative adjusted differences in expenditures were US$9991 and 42% of population mean expenditure ( P EOL care intensity measures, teachers (5 of 5), homemakers (4 of 5), farmers (4 of 5), and clergy (3 of 5) demonstrated significantly less aggressive care. Mortuary workers had lower EOL care intensity (4 of 5) but small numbers limited statistical significance. Occupations with likely exposure to child development, death/bereavement, and naturalistic influences demonstrated lower EOL care intensity. These findings may inform patients and clinicians navigating choices around individual EOL care preferences.

  13. Applications for coupled core neutronics and thermal-hydraulic models

    International Nuclear Information System (INIS)

    Eller, J.

    1996-01-01

    The unprecedented increases in computing capacity that have occurred during the last decade have affected our sciences, and thus our lives, to an extent that is difficult to overstate. All indications are that this trend will continue for years to come. Nuclear reactor systems analysis is one of many areas of engineering that has changed dramatically as a result of this evolution. Our ability to model the various mechanical and physical systems in greater and greater detail has allowed significant improvements in operational efficiency in spite of increasing regulatory requirements. Many of these efficiencies result from the use of more complex and geometrically detailed computer modeling, which is used to justify a reduction or elimination of some of the conservatisms required by earlier, less sophisticated analyses. And more recently, as our industries open-quotes downsize,close quotes efforts are being made to find ways to use the ever-increasing computing capacity to design systems that accomplish more work, in less time, and with fewer people. The balance of this paper discusses some of the visions that Duke Power Company feels would most benefit their particular methodologies. One of the concepts receiving a lot of attention involves an automated coupling of a thermal-hydraulic plant systems analysis model to a three-dimensional core neutronics program. The thermal-hydraulic analysis of several postulated system transients incorporates large conservatisms because of limited ability to model complex time-dependent asymmetric heat sources in adequate geometric detail. For these transients, the core behavior is closely coupled with the thermal-hydraulic behavior of the total plant system and vice versa. Steam-line break, uncontrolled rod withdrawal, and rod drop anayses are likely to benefit most from this type of linked process

  14. INL Experimental Program Roadmap for Thermal Hydraulic Code Validation

    Energy Technology Data Exchange (ETDEWEB)

    Glenn McCreery; Hugh McIlroy

    2007-09-01

    Advanced computer modeling and simulation tools and protocols will be heavily relied on for a wide variety of system studies, engineering design activities, and other aspects of the Next Generation Nuclear Power (NGNP) Very High Temperature Reactor (VHTR), the DOE Global Nuclear Energy Partnership (GNEP), and light-water reactors. The goal is for all modeling and simulation tools to be demonstrated accurate and reliable through a formal Verification and Validation (V&V) process, especially where such tools are to be used to establish safety margins and support regulatory compliance, or to design a system in a manner that reduces the role of expensive mockups and prototypes. Recent literature identifies specific experimental principles that must be followed in order to insure that experimental data meet the standards required for a “benchmark” database. Even for well conducted experiments, missing experimental details, such as geometrical definition, data reduction procedures, and manufacturing tolerances have led to poor Benchmark calculations. The INL has a long and deep history of research in thermal hydraulics, especially in the 1960s through 1980s when many programs such as LOFT and Semiscle were devoted to light-water reactor safety research, the EBRII fast reactor was in operation, and a strong geothermal energy program was established. The past can serve as a partial guide for reinvigorating thermal hydraulic research at the laboratory. However, new research programs need to fully incorporate modern experimental methods such as measurement techniques using the latest instrumentation, computerized data reduction, and scaling methodology. The path forward for establishing experimental research for code model validation will require benchmark experiments conducted in suitable facilities located at the INL. This document describes thermal hydraulic facility requirements and candidate buildings and presents examples of suitable validation experiments related

  15. Thermal hydraulic behavior evaluation of tank A-101

    International Nuclear Information System (INIS)

    Ogden, D.M.

    1996-01-01

    This report describes a new evaluation conducted to help understand the thermal-hydraulic behavior of tank A-101. Prior analysis of temperature data indicated that the dome space and upper waste layer was slowly increasing in temperature increases are due to increasing ambient temperatures and termination of forced ventilation. However, this analysis also indicates that other dome cooling processes are slowly decreasing, or some slow increase in heating is occurring at the waste surface. Dome temperatures are not decreasing at the rate expected as a forced ventilation termination effects are accounted for

  16. First wall thermal hydraulic models for fusion blankets

    International Nuclear Information System (INIS)

    Fillo, J.A.

    1980-01-01

    Subject to normal and off-normal reactor conditions, thermal hydraulic models of first walls, e.g., a thermal mass barrier, a tubular shield, and a radiating liner are reviewed. Under normal operation the plasma behaves as expected in a predicted way for transient and steady-state conditions. The most severe thermal loading on the first wall occurs when the plasma becomes unstable and dumps its energy on the wall in a very short period of time (milliseconds). Depending on the plasma dump time and area over which the energy is deposited may result in melting of the first wall surface, and if the temperature is high enough, vaporization

  17. Thermal-hydraulic analysis of PWR cores in transient condition

    International Nuclear Information System (INIS)

    Silva Galetti, M.R. da.

    1984-01-01

    A calculational methodology for thermal - hydraulic analysis of PWR cores under steady-state and transient condition was selected and made available to users. An evaluation of the COBRA-IIIP/MIT code, used for subchannel analysis, was done through comparison of the code results with experimental data on steady state and transient conditions. As a result, a comparison study allowing spatial and temporal localization of critical heat flux was obtained. A sensitivity study of the simulation model to variations in some empirically determined parameter is also presented. Two transient cases from Angra I FSAR were analysed, showing the evolution of minimum DNBR with time. (Author) [pt

  18. Current Development and Trends in Thermal-Hydraulics

    International Nuclear Information System (INIS)

    Toth, I.

    2008-01-01

    A review of CSNI activities during the last two decades in the field of thermal-hydraulics and related topics has been extensively presented in sessions 2. to 9. New activities are in progress or planned partly based on recommendations of the CSNI Operating Plan and the CSNI SESAR SFEAR report, but also on requests coming from the member states. These activities are performed in the frame of the CSNI Working Group on the Analysis and Management of Accidents (GAMA) or in the frame of CSNI Projects. These actions are summarized in this paper.

  19. Project W-320 thermal hydraulic model benchmarking and baselining

    International Nuclear Information System (INIS)

    Sathyanarayana, K.

    1998-01-01

    Project W-320 will be retrieving waste from Tank 241-C-106 and transferring the waste to Tank 241-AY-102. Waste in both tanks must be maintained below applicable thermal limits during and following the waste transfer. Thermal hydraulic process control models will be used for process control of the thermal limits. This report documents the process control models and presents a benchmarking of the models with data from Tanks 241-C-106 and 241-AY-102. Revision 1 of this report will provide a baselining of the models in preparation for the initiation of sluicing

  20. Thermal-hydraulic considerations for particle bed reactors

    Science.gov (United States)

    Benenati, R.; Araj, K. J.; Horn, F.

    In the design of particle bed reactor (PBR) cores, consideration must be given to the gas coolant channels and their configuration. Neutronics analysis provides the relative volume fractions of the component materials, but these must be arranged in such a manner as to allow proper cooling of all components by the gas flow at relatively low pressure drops. The thermal hydraulic aspects of this problem are addressed. A description of the computer model used in the analysis of the steady state condition is also included. Blowdown tests on hot particle bed fuel elements were carried out and are described.

  1. Study of thermal - hydraulic sensors signal fluctuations in PWR

    International Nuclear Information System (INIS)

    Hennion, F.

    1987-10-01

    This thesis deals with signal fluctuations of thermal-hydraulic sensors in the main coolant primary of a pressurized water reactor. The aim of this work is to give a first response about the potentiality of use of these noise signals for the functionning monitoring. Two aspects have been studied: - the modelisation of temperature fluctuations of core thermocouples, by a Monte-Carlo method, gives the main characteristics of these signals and their domain of application. - the determination of eigenfrequency in the primary by an acoustic representation could permit the monitoring of local and global thermo-hydraulic conditions [fr

  2. Thermal hydraulic behavior of SCWR sliding pressure startup

    International Nuclear Information System (INIS)

    Fu Shengwei; Zhou Chong; Xu Zhihong; Yang Yanhua

    2011-01-01

    The modification to ATHLET-SC code is introduced in this paper, which realizes the simulation of trans-critical transients using two-phase model. With the modified code, the thermal-hydraulic dynamic behavior of the mixed SCWR core during the startup process is simulated. The startup process is similar to the design of SCLWR-H sliding pressure startup. The results show that maximum temperature of cladding-surface does not exceed 650℃ in the whole startup process, and the sudden change of water properties in the trans-critical transients will not cause harmful influence to the heat transfer of the fuel cladding. (authors)

  3. PHENIX Muon Arms

    International Nuclear Information System (INIS)

    Akikawa, H.; Al-Jamel, A.; Archuleta, J.B.; Archuleta, J.R.; Armendariz, R.; Armijo, V.; Awes, T.C.; Baldisseri, A.; Barker, A.B.; Barnes, P.D.; Bassalleck, B.; Batsouli, S.; Behrendt, J.; Bellaiche, F.G.; Bland, A.W.; Bobrek, M.; Boissevain, J.G.; Borel, H.; Brooks, M.L.; Brown, A.W.; Brown, D.S.; Bruner, N.; Cafferty, M.M.; Carey, T.A.; Chai, J.-S.; Chavez, L.L.; Chollet, S.; Choudhury, R.K.; Chung, M.S.; Cianciolo, V.; Clark, D.J.; Cobigo, Y.; Dabrowski, C.M.; Debraine, A.; DeMoss, J.; Dinesh, B.V.; Drachenberg, J.L.; Drapier, O.; Echave, M.A.; Efremenko, Y.V.; En'yo, H.; Fields, D.E.; Fleuret, F.; Fried, J.; Fujisawa, E.; Funahashi, H.; Gadrat, S.; Gastaldi, F.; Gee, T.F.; Glenn, A.; Gogiberidze, G.; Gonin, M.; Gosset, J.; Goto, Y.; Granier de Cassagnac, R.; Hance, R.H.; Hart, G.W.; Hayashi, N.; Held, S.; Hicks, J.S.; Hill, J.C.; Hoade, R.; Hong, B.; Hoover, A.; Horaguchi, T.; Hunter, C.T.; Hurst, D.E.; Ichihara, T.; Imai, K.; Isenhower, L.D.L. Davis; Isenhower, L.D.L. Donald; Ishihara, M.; Jang, W.Y.; Johnson, J.; Jouan, D.; Kamihara, N.; Kamyshkov, Y.; Kang, J.H.; Kapoor, S.S.; Kim, D.J.; Kim, D.-W.; Kim, G.-B.; Kinnison, W.W.; Klinksiek, S.; Kluberg, L.; Kobayashi, H.; Koehler, D.; Kotchenda, L.; Kuberg, C.H.; Kurita, K.; Kweon, M.J.; Kwon, Y.; Kyle, G.S.; LaBounty, J.J.; Lajoie, J.G.; Lee, D.M.; Lee, S.; Leitch, M.J.; Li, Z.; Liu, M.X.; Liu, X.; Liu, Y.; Lockner, E.; Lopez, J.D.; Mao, Y.; Martinez, X.B.; McCain, M.C.; McGaughey, P.L.; Mioduszewski, S.; Mischke, R.E.; Mohanty, A.K.; Montoya, B.C.; Moss, J.M.; Murata, J.; Murray, M.M.; Nagle, J.L.; Nakada, Y.; Newby, J.; Obenshain, F.; Palounek, A.P.T.; Papavassiliou, V.; Pate, S.F.; Plasil, F.; Pope, K.; Qualls, J.M.; Rao, G.; Read, K.F.; Robinson, S.H.; Roche, G.; Romana, A.; Rosnet, P.; Roth, R.; Saito, N.; Sakuma, T.; Sandhoff, W.F.; Sanfratello, L.; Sato, H.D.; Savino, R.; Sekimoto, M.; Shaw, M.R.; Shibata, T.-A.; Sim, K.S.; Skank, H.D.; Smith, D.E.; Smith, G.D.; Sondheim, W.E.; Sorensen, S.; Staley, F.; Stankus, P.W.; Steffens, S.; Stein, E.M.; Stepanov, M.; Stokes, W.; Sugioka, M.; Sun, Z.; Taketani, A.; Taniguchi, E.; Tepe, J.D.; Thornton, G.W.; Tian, W.; Tojo, J.; Torii, H.; Towell, R.S.; Tradeski, J.; Vassent, M.; Velissaris, C.; Villatte, L.; Wan, Y.; Watanabe, Y.; Watkins, L.C.; Whitus, B.R.; Williams, C.; Willis, P.S.; Wong-Swanson, B.G.; Yang, Y.; Yoneyama, S.; Young, G.R.; Zhou, S.

    2003-01-01

    The PHENIX Muon Arms detect muons at rapidities of |y|=(1.2-2.4) with full azimuthal acceptance. Each muon arm must track and identify muons and provide good rejection of pions and kaons (∼10 -3 ). In order to accomplish this we employ a radial field magnetic spectrometer with precision tracking (Muon Tracker) followed by a stack of absorber/low resolution tracking layers (Muon Identifier). The design, construction, testing and expected run parameters of both the muon tracker and the muon identifier are described

  4. PHENIX Muon Arms

    Energy Technology Data Exchange (ETDEWEB)

    Akikawa, H.; Al-Jamel, A.; Archuleta, J.B.; Archuleta, J.R.; Armendariz, R.; Armijo, V.; Awes, T.C.; Baldisseri, A.; Barker, A.B.; Barnes, P.D.; Bassalleck, B.; Batsouli, S.; Behrendt, J.; Bellaiche, F.G.; Bland, A.W.; Bobrek, M.; Boissevain, J.G.; Borel, H.; Brooks, M.L.; Brown, A.W.; Brown, D.S.; Bruner, N.; Cafferty, M.M.; Carey, T.A.; Chai, J.-S.; Chavez, L.L.; Chollet, S.; Choudhury, R.K.; Chung, M.S.; Cianciolo, V.; Clark, D.J.; Cobigo, Y.; Dabrowski, C.M.; Debraine, A.; DeMoss, J.; Dinesh, B.V.; Drachenberg, J.L.; Drapier, O.; Echave, M.A.; Efremenko, Y.V.; En' yo, H.; Fields, D.E.; Fleuret, F.; Fried, J.; Fujisawa, E.; Funahashi, H.; Gadrat, S.; Gastaldi, F.; Gee, T.F.; Glenn, A.; Gogiberidze, G.; Gonin, M.; Gosset, J.; Goto, Y.; Granier de Cassagnac, R.; Hance, R.H.; Hart, G.W.; Hayashi, N.; Held, S.; Hicks, J.S.; Hill, J.C.; Hoade, R.; Hong, B.; Hoover, A.; Horaguchi, T.; Hunter, C.T.; Hurst, D.E.; Ichihara, T.; Imai, K.; Isenhower, L.D.L. Davis; Isenhower, L.D.L. Donald; Ishihara, M.; Jang, W.Y.; Johnson, J.; Jouan, D.; Kamihara, N.; Kamyshkov, Y.; Kang, J.H.; Kapoor, S.S.; Kim, D.J.; Kim, D.-W.; Kim, G.-B.; Kinnison, W.W.; Klinksiek, S.; Kluberg, L.; Kobayashi, H.; Koehler, D.; Kotchenda, L.; Kuberg, C.H.; Kurita, K.; Kweon, M.J.; Kwon, Y.; Kyle, G.S.; LaBounty, J.J.; Lajoie, J.G.; Lee, D.M.; Lee, S.; Leitch, M.J.; Li, Z.; Liu, M.X.; Liu, X.; Liu, Y.; Lockner, E.; Lopez, J.D.; Mao, Y.; Martinez, X.B.; McCain, M.C.; McGaughey, P.L.; Mioduszewski, S.; Mischke, R.E.; Mohanty, A.K.; Montoya, B.C.; Moss, J.M.; Murata, J.; Murray, M.M.; Nagle, J.L.; Nakada, Y.; Newby, J.; Obenshain, F.; Palounek, A.P.T.; Papavassiliou, V.; Pate, S.F.; Plasil, F.; Pope, K.; Qualls, J.M.; Rao, G.; Read, K.F. E-mail: readkf@ornl.gov; Robinson, S.H.; Roche, G.; Romana, A.; Rosnet, P.; Roth, R.; Saito, N.; Sakuma, T.; Sandhoff, W.F.; Sanfratello, L.; Sato, H.D.; Savino, R.; Sekimoto, M.; Shaw, M.R.; Shibata, T.-A.; Sim, K.S.; Skank, H.D.; Smith, D.E.; Smith, G.D. [and others

    2003-03-01

    The PHENIX Muon Arms detect muons at rapidities of |y|=(1.2-2.4) with full azimuthal acceptance. Each muon arm must track and identify muons and provide good rejection of pions and kaons ({approx}10{sup -3}). In order to accomplish this we employ a radial field magnetic spectrometer with precision tracking (Muon Tracker) followed by a stack of absorber/low resolution tracking layers (Muon Identifier). The design, construction, testing and expected run parameters of both the muon tracker and the muon identifier are described.

  5. Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model

    Directory of Open Access Journals (Sweden)

    Reza Akbari

    2017-08-01

    Full Text Available Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the distribution of heat sources, which is needed to perform the thermal-hydraulic analysis. In this study single heated channel model as a very fast model for predicting thermal hydraulics behavior of pressurized water reactor core has been developed. For verifying the results of this model, we used RELAP5 code as US nuclear regulatory approved thermal hydraulics code. The results of developed single heated channel model have been checked with RELAP5 results for WWER-1000. This comparison shows the capability of single heated channel model for predicting thermal hydraulics behavior of reactor core.

  6. A Study on thermal-hydraulic characteristics of the coolant materials for the transmutation reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Chang Hyun; You, Young Woo; Cho, Jae Seon; Kim, Ju Youl; Kim, Do Hyoung; Kim, Yoon Ik; Yang, Hui Chang [Seoul National University, Taejon (Korea)

    1998-03-01

    The objective of this study is to provide the direction of transmutation reactor design in terms of thermal hydraulics especially through the analysis of thermal hydraulic characteristics of various candidate materials for the transmutation reactor coolant. In this study, the characteristics of coolant materials used in current nuclear power plants and candidate materials for transmutation reactor are analyzed and compared. To evaluate the thermal hydraulic characteristics, the preliminary thermal-hydraulic calculation is performed for the candidate coolant materials of transmutation reactor. An analysis of thermal-hydraulic characteristics of transmutation reactor. An analysis of thermal-hydraulic characteristics of Sodium, Lead, Lead-Bismuth, and Lead-Lithium among the liquid metals considered as the coolant of transmutation reactor is performed by using computational fluid dynamics code FLUENT, and SIMPLER algorithm. (author). 50 refs., 40 figs., 30 tabs.

  7. Cross-cutting european thermal-hydraulics research for innovative nuclear systems

    International Nuclear Information System (INIS)

    Roelofs, F.; Class, A.; Cheng, X.; Meloni, P.; Van Tichelen, K.; Boudier, P.; Prasser, M.

    2010-01-01

    Thermal-hydraulics is recognized as a key scientific subject in the development of different innovative nuclear reactor systems. From the thermal-hydraulic point of view, different innovative reactors are mainly characterized by their coolants (gas, water, liquid metals and molten salt). This results in different micro- and macroscopic behavior of flow and heat transfer and requires specific models and advanced analysis tools. However, many common thermal-hydraulic issues are identified among various innovative nuclear systems. In Europe, such cross-cutting thermal-hydraulic issues are the subject of the 7. framework programme THINS (Thermal-Hydraulics of Innovative Nuclear Systems) project which runs from 2010 until 2014. This paper will describe the activities in this project which address the main identified thermal hydraulics issues for innovative nuclear systems. (authors)

  8. Impressive Super Phenix

    International Nuclear Information System (INIS)

    Olds, F.C.

    1979-01-01

    The 1200-MWe fast breeder reactor, Super Phenix at Creys-Malville, is scheduled for commercial operation in 1983. This is the world's first near-commercial-sized fast breeder. As a near-commercial-sized unit, it represents essentially the technology and hardware of the first fully commercial follow-on units. In its size, its components, its design, the technology it represents, and its project schedule, it is impressive. As of May 1979, the Super Phenix nuclear steam boiler in the Creys-Malville plant bore an estimated cost of $700 million, without fuel. The total cost of the Creys-Malville plant now is estimated at about $1.4 billion. This is about twice the cost of a comparable standardized PWR being built in France today. However, it should be borne in mind that Creys-Malville carries the high cost of a first-of-the-line prototype, and that France's PWRs are standardized, second-generation units. Electricity from Creys-Malville is estimated to cost a little more than electricity would cost from a coal-fired plant complete with flue gas scrubbing

  9. Thermal-hydraulic modeling needs for passive reactors

    International Nuclear Information System (INIS)

    Kelly, J.M.

    1997-01-01

    The U.S. Nuclear Regulatory Commission has received an application for design certification from the Westinghouse Electric Corporation for an Advanced Light Water Reactor design known as the AP600. As part of the design certification process, the USNRC uses its thermal-hydraulic system analysis codes to independently audit the vendor calculations. The focus of this effort has been the small break LOCA transients that rely upon the passive safety features of the design to depressurize the primary system sufficiently so that gravity driven injection can provide a stable source for long term cooling. Of course, large break LOCAs have also been considered, but as the involved phenomena do not appear to be appreciably different from those of current plants, they were not discussed in this paper. Although the SBLOCA scenario does not appear to threaten core coolability - indeed, heatup is not even expected to occur - there have been concerns as to the performance of the passive safety systems. For example, the passive systems drive flows with small heads, consequently requiring more precision in the analysis compared to active systems methods for passive plants as compared to current plants with active systems. For the analysis of SBLOCAs and operating transients, the USNRC uses the RELAP5 thermal-hydraulic system analysis code. To assure the applicability of RELAP5 to the analysis of these transients for the AP600 design, a four year long program of code development and assessment has been undertaken

  10. Alternative solution algorithm for coupled thermal-hydraulic problems

    International Nuclear Information System (INIS)

    Farnsworth, D.A.; Rice, J.G.

    1986-01-01

    A thermal-hydraulic system involves flow of a fluid for which a combined solution of the continuity, momentum, and energy equations is required. When the solutions of the energy and momentum fields are dependent on each other, the system is said to be thermally coupled. A common problem encountered in the numerical solution of strongly coupled thermal-hydraulic problems is a very slow rate of convergence or a complete lack of convergence. Many times this degradation in convergence is due to the lack of true coupling between the energy and momentum fields during the iteration process. In the most widely used solution algorithms - such as the SIMPLE algorithm and its many variants - a sequential solution technique is required. That is, the solution process alternates between the flow and energy fields until a converged solution is obtained. This approach allows only implicit energy-momentum coupling. To improve the convergence rate for strongly coupled problems, a practical solution algorithm that can accommodate true energy-momentum coupling terms was developed. A complete simultaneous (versus sequential) solution of the governing conservation equations utilizing a line-by-line solution was developed and direct coupling terms between the momentum and energy fields were added utilizing a modified Newton-Raphson technique

  11. Thermal-hydraulic modeling of porous bed reactors

    International Nuclear Information System (INIS)

    Araj, K.J.; Nourbakhsh, H.P.

    1987-01-01

    Optimum design of nuclear reactor cores requires an iterative approach between the thermal-hydraulic, neutronic, and operational analysis. This paper will concentrate on the thermal-hydraulic behavior of a hydrogen-cooled small particle bed reactor (PBR). The PBR core modeled here consists of a hexagonal array of fuel elements embedded in a moderator matrix. The fuel elements are annular packed beds of fuel particles held between two porous cylindrical frits. These particles, 500 to 600 μm in diameter, have a uranium carbide core, which is coated by two layers of graphite and an outer coating of zirconium carbide. Coolant flows, radially inward, from the cold frit through the packed bed and hot frit and axially out the channel, formed by the hot frit to a common plenum. A fast running one-dimensional lumped-parameter steady-state code (FTHP) was developed to evaluate the effects of design changes in fuel assembly and power distribution. Another objective for the code was to investigate various methods of coolant control to minimize hot channel effects and maximize outlet temperatures

  12. Thermal hydraulics analysis of LIBRA-SP target chamber

    International Nuclear Information System (INIS)

    Mogahed, E.A.

    1996-01-01

    LIBRA-SP is a conceptual design study of an inertially confined 1000 MWe fusion power reactor utilizing self-pinched light ion beams. There are 24 ion beams which are arranged around the reactor cavity. The reaction chamber is an upright cylinder with an inverted conical roof resembling a mushroom, and a pool floor. The vertical sides of the cylinder are occupied by a blanket zone consisting of many perforated rigid HT-9 ferritic steel tubes called PERITs (PEr-forated RIgid Tube). The breeding/cooling material, liquid lead-lithium, flows through the PERITs, providing protection to the reflector/vacuum chamber so as to make it a lifetime component. The neutronics analysis and cavity hydrodynamics calculations are performed to account for the neutron heating and also to determine the effects of vaporization/condensation processes on the surface heat flux. The steady state nuclear heating distribution at the midplane is used for thermal hydraulics calculations. The maximum surface temperature of the HT-9 is chosen to not exceed 625 degree C to avoid drastic deterioration of the metal's mechanical properties. This choice restricts the thermal hydraulics performance of the reaction cavity. The inlet first surface coolant bulk temperature is 370 degree C, and the heat exchanger inlet coolant bulk temperature is 502 degree C. 4 refs., 6 figs., 2 tabs

  13. Thermal hydraulic and safety analyses for Pakistan Research Reactor-1

    International Nuclear Information System (INIS)

    Bokhari, I.H.; Israr, M.; Pervez, S.

    1999-01-01

    Thermal hydraulic and safety analysis of Pakistan Research Reactor-1 (PARR-1) utilizing low enriched uranium (LEU) fuel have been performed using computer code PARET. The present core comprises of 29 standard and 5 control fuel elements. Results of the thermal hydraulic analysis show that the core can be operated at a steady-state power level of 10 MW for a flow rate of 950 m 3 /h, with sufficient safety margins against ONB (onset of nucleate boiling) and DNB (departure from nucleate boiling). Safety analysis has been carried out for various modes of reactivity insertions. The events studied include: start-up accident; accidental drop of a fuel element in the core; flooding of a beam tube with water; removal of an in-pile experiment during reactor operation etc. For each of these transients, time histories of reactor power, energy released and clad surface temperature etc. were calculated. The results indicate that the peak clad temperatures remain well below the clad melting temperature during these accidents. It is therefore concluded that the reactor can be safely operated at 10 MW without compromising safety. (author)

  14. Thermal-hydraulic modeling needs for passive reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, J.M. [Nuclear Regulatory Commission, Washington, DC (United States)

    1997-07-01

    The U.S. Nuclear Regulatory Commission has received an application for design certification from the Westinghouse Electric Corporation for an Advanced Light Water Reactor design known as the AP600. As part of the design certification process, the USNRC uses its thermal-hydraulic system analysis codes to independently audit the vendor calculations. The focus of this effort has been the small break LOCA transients that rely upon the passive safety features of the design to depressurize the primary system sufficiently so that gravity driven injection can provide a stable source for long term cooling. Of course, large break LOCAs have also been considered, but as the involved phenomena do not appear to be appreciably different from those of current plants, they were not discussed in this paper. Although the SBLOCA scenario does not appear to threaten core coolability - indeed, heatup is not even expected to occur - there have been concerns as to the performance of the passive safety systems. For example, the passive systems drive flows with small heads, consequently requiring more precision in the analysis compared to active systems methods for passive plants as compared to current plants with active systems. For the analysis of SBLOCAs and operating transients, the USNRC uses the RELAP5 thermal-hydraulic system analysis code. To assure the applicability of RELAP5 to the analysis of these transients for the AP600 design, a four year long program of code development and assessment has been undertaken.

  15. Thermal Hydraulic Analysis on Containment Filtered Venting System

    Energy Technology Data Exchange (ETDEWEB)

    Bang, Young Suk; Park, Tong Kyu; Lee, Doo Yong; Lee, Byung Chul [FNC Technology Co. Ltd., Yongin (Korea, Republic of); Lee, Sang Won; Kim, Hyeong Taek [KHNP-Central Research Institute, Daejeon (Korea, Republic of)

    2014-05-15

    In this study, the thermal hydraulic conditions (e. g. pressure and flow rate) at each component have been examined and the sensitivity analysis on CFVS design parameters (e. g. water inventory, volumetric flow rate). The purpose is to know the possible range of flow conditions at each component to determine the optimum size of filtration system. GOTHIC code has been used to simulate the thermal-hydraulic behavior inside of CFVS. The behavior of flows in the CFVS has been investigated. The vessel water level and the flow rates during the CFVS operation are examined. It was observed that the vessel water level would be changed significantly due to steam condensation/thermal expansion and steam evaporation. Therefore, the vessel size and the initial water inventory should be carefully determined to keep the minimum water level required for filtration components and not to flood the components in the upper side of the vessel. It has been also observed that the volumetric flow rate is maintained during the CFVS operation, which is beneficial for pool scrubbing units. However, regarding the significant variations at the orifice downstream, careful design would be necessary.

  16. Thermal hydraulic analysis of BWR containment venting system

    International Nuclear Information System (INIS)

    Baburajan, P.K.; Sharma, Prashant; Paul, U.K.; Gaikwad, Avinash

    2015-01-01

    Installation of additional containment filtered venting system (CFVS) is necessary to depressurize the containment to maintain its mechanical integrity due to over pressurization during severe accident condition. A typical venting system for BWR is modelled using RELAP5 and analysed to investigate the effect of various thermal hydraulic parameters on the operational parameters of the venting system. The venting system consists of piping from the containment to the scrubber tank and exit line from the scrubber tank. The scrubber tank is partially filled with water to enable the scrubbing action to remove the particulate radionuclides from the incoming containment air. The pipe line from the containment is connected to the venturi inlet and the throat of the venturi is open to the scrubber tank water inventory at designed submergence level. The exit of the venturi is open to scrubber tank water. Filters are used in the upper air space of the scrubber tank as mist separator before venting out the air into the atmosphere through the exit vent line. The effect of thermal hydraulic parameters such as inlet fluid temperature, inlet steam content and venturi submergence in the scrubber tank on the venting flow rate, exit steam content, scrubber tank inventory, overflow line and siphon breaker flow rate is analysed. Results show that inlet steam content and the venturi nozzle submergence influence the venting system parameters. (author)

  17. LWR containment thermal hydraulic codes benchmark demona B3 exercise

    International Nuclear Information System (INIS)

    Della Loggia, E.; Gauvain, J.

    1988-01-01

    Recent discussion about the aerosol codes currently used for the analysis of containment retention capabilities have revealed a number of questions concerning the reliabilities and verifications of the thermal-hydraulic modules of these codes with respect to the validity of implemented physical models and the stability and effectiveness of numerical schemes. Since these codes are used for the calculation of the Source Term for the assessment of radiological consequences of severe accidents, they are an important part of reactor safety evaluation. For this reason the Commission of European Communities (CEC), following the recommendation mode by experts from Member Stades, is promoting research in this field with the aim also of establishing and increasing collaboration among Research Organisations of member countries. In view of the results of the studies, the CEC has decided to carry out a Benchmark exercise for severe accident containment thermal hydraulics codes. This exercise is based on experiment B3 in the DEMONA programme. The main objective of the benchmark exercise has been to assess the ability of the participating codes to predict atmosphere saturation levels and bulk condensation rates under conditions similar to those predicted to follow a severe accident in a PWR. This exercise follows logically on from the LA-4 exercise, which, is related to an experiment with a simpler internal geometry. We present here the results obtained so far and from them preliminary conclusions are drawn, concerning condensation temperature, pressure, flow rates, in the reactor containment

  18. Finite volume thermal-hydraulics and neutronics coupled calculations - 15300

    International Nuclear Information System (INIS)

    Araujo Silva, V.; Campagnole dos Santos, A.A.; Mesquit, A.Z.; Bernal, A.; Miro, R.; Verdu, G.; Pereira, C.

    2015-01-01

    The computational power available nowadays allows the coupling of neutronics and thermal-hydraulics codes for reactor studies. The present methodology foresees at least one constraint to the separated codes in order to perform coupled calculations: both codes must use the same geometry, however, meshes can be different for each code as long as the internal surfaces stays the same. Using the finite volume technique, a 3D diffusion nodal code was implemented to deal with neutron transport. This code can handle non-structured meshes which allows for complicated geometries calculations and therefore more flexibility. A computational fluid dynamics (CFD) code was used in order to obtain the same level of details for the thermal hydraulics calculations. The chosen code is OpenFOAM, an open-source CFD tool. Changes in OpenFOAM allow simple coupled calculations of a PWR fuel rod with neutron transport code. OpenFOAM sends coolant density information and fuel temperature to the neutron transport code that sends back power information. A mapping function is used to average values when one node in one side corresponds to many nodes in the other side. Data is exchanged between codes by library calls. As the results of a fuel rod calculations progress, more complicated and processing demanding geometries will be simulated, aiming to the simulation of a real scale PWR fuel assembly

  19. Advanced modelling and numerical strategies in nuclear thermal-hydraulics

    International Nuclear Information System (INIS)

    Staedtke, H.

    2001-01-01

    The first part of the lecture gives a brief review of the current status of nuclear thermal hydraulics as it forms the basis of established system codes like TRAC, RELAP5, CATHARE or ATHLET. Specific emphasis is given to the capabilities and limitations of the underlying physical modelling and numerical solution strategies with regard to the description of complex transient two-phase flow and heat transfer conditions as expected to occur in PWR reactors during off-normal and accident conditions. The second part of the lecture focuses on new challenges and future needs in nuclear thermal-hydraulics which might arise with regard to re-licensing of old plants using bestestimate methodologies or the design and safety analysis of Advanced Light Water Reactors relying largely on passive safety systems. In order to meet these new requirements various advanced modelling and numerical techniques will be discussed including extended wellposed (hyperbolic) two-fluid models, explicit modelling of interfacial area transport or higher order numerical schemes allowing a high resolution of local multi-dimensional flow processes.(author)

  20. Scaling of Thermal-Hydraulic Phenomena and System Code Assessment

    International Nuclear Information System (INIS)

    Wolfert, K.

    2008-01-01

    In the last five decades large efforts have been undertaken to provide reliable thermal-hydraulic system codes for the analyses of transients and accidents in nuclear power plants. Many separate effects tests and integral system tests were carried out to establish a data base for code development and code validation. In this context the question has to be answered, to what extent the results of down-scaled test facilities represent the thermal-hydraulic behaviour expected in a full-scale nuclear reactor under accidental conditions. Scaling principles, developed by many scientists and engineers, present a scientific technical basis and give a valuable orientation for the design of test facilities. However, it is impossible for a down-scaled facility to reproduce all physical phenomena in the correct temporal sequence and in the kind and strength of their occurrence. The designer needs to optimize a down-scaled facility for the processes of primary interest. This leads compulsorily to scaling distortions of other processes with less importance. Taking into account these weak points, a goal oriented code validation strategy is required, based on the analyses of separate effects tests and integral system tests as well as transients occurred in full-scale nuclear reactors. The CSNI validation matrices are an excellent basis for the fulfilling of this task. Separate effects tests in full scale play here an important role.

  1. Teaching Thermal Hydraulics & Numerical Methods: An Introductory Control Volume Primer

    Energy Technology Data Exchange (ETDEWEB)

    D. S. Lucas

    2004-10-01

    A graduate level course for Thermal Hydraulics (T/H) was taught through Idaho State University in the spring of 2004. A numerical approach was taken for the content of this course since the students were employed at the Idaho National Laboratory and had been users of T/H codes. The majority of the students had expressed an interest in learning about the Courant Limit, mass error, semi-implicit and implicit numerical integration schemes in the context of a computer code. Since no introductory text was found the author developed notes taught from his own research and courses taught for Westinghouse on the subject. The course started with a primer on control volume methods and the construction of a Homogeneous Equilibrium Model (HEM) (T/H) code. The primer was valuable for giving the students the basics behind such codes and their evolution to more complex codes for Thermal Hydraulics and Computational Fluid Dynamics (CFD). The course covered additional material including the Finite Element Method and non-equilibrium (T/H). The control volume primer and the construction of a three-equation (mass, momentum and energy) HEM code are the subject of this paper . The Fortran version of the code covered in this paper is elementary compared to its descendants. The steam tables used are less accurate than the available commercial version written in C Coupled to a Graphical User Interface (GUI). The Fortran version and input files can be downloaded at www.microfusionlab.com.

  2. Minerve: thermal-hydraulic phenomena simulation and virtual reality

    International Nuclear Information System (INIS)

    Laffont, A.; Pentori, B.

    2003-01-01

    MINERVE is a 3D interactive application representing the thermal-hydraulic phenomena happening in a nuclear plant. Therefore, the 3D geometric model of the French 900 MW PWR installations has been built. The users can interact in real time with this model to see at each step of the simulation what happens in the pipes. The thermal-hydraulic simulation is made by CATHARE-2, which calculates at every time step data on about one thousand meshes (the whole primary circuit, a part of the second circuit, and the Residual Heat Removal System). The simulation covers incidental and accidental cases on these systems. There are two main innovations in MINERVE: In the domain of nuclear plant's visualization, it is to introduce interactive 3D software mechanisms to visualize results of a physical simulation. In the domain of real-time 3D, it is to visualize fluids in a pipe, while they can have several configurations, like bubbles or single liquid phase. These mechanisms enable better comprehension and better visual representation of the possible phenomena. This paper describes the functionalities of MINERVE, and the difficulties to represent fluids with several characteristics like speed, configuration,..., in 3D. On the end, we talk about the future of MINERVE, and more widely of the possible futures of such an application in scientific visualization. (authors)

  3. Minerve: thermal-hydraulic phenomena simulation and virtual reality

    Energy Technology Data Exchange (ETDEWEB)

    Laffont, A.; Pentori, B. [EDF R and D, EDF SEPTEN Electricity of France - Research and Development, Department SINETICS, 92 - Clamart (France)

    2003-07-01

    MINERVE is a 3D interactive application representing the thermal-hydraulic phenomena happening in a nuclear plant. Therefore, the 3D geometric model of the French 900 MW PWR installations has been built. The users can interact in real time with this model to see at each step of the simulation what happens in the pipes. The thermal-hydraulic simulation is made by CATHARE-2, which calculates at every time step data on about one thousand meshes (the whole primary circuit, a part of the second circuit, and the Residual Heat Removal System). The simulation covers incidental and accidental cases on these systems. There are two main innovations in MINERVE: In the domain of nuclear plant's visualization, it is to introduce interactive 3D software mechanisms to visualize results of a physical simulation. In the domain of real-time 3D, it is to visualize fluids in a pipe, while they can have several configurations, like bubbles or single liquid phase. These mechanisms enable better comprehension and better visual representation of the possible phenomena. This paper describes the functionalities of MINERVE, and the difficulties to represent fluids with several characteristics like speed, configuration,..., in 3D. On the end, we talk about the future of MINERVE, and more widely of the possible futures of such an application in scientific visualization. (authors)

  4. International benchmark on the natural convection test in Phenix reactor

    International Nuclear Information System (INIS)

    Tenchine, D.; Pialla, D.; Fanning, T.H.; Thomas, J.W.; Chellapandi, P.; Shvetsov, Y.; Maas, L.; Jeong, H.-Y.; Mikityuk, K.; Chenu, A.; Mochizuki, H.; Monti, S.

    2013-01-01

    Highlights: ► Phenix main characteristics, instrumentation and natural convection test are described. ► “Blind” calculations and post-test calculations from all the participants to the benchmark are compared to reactor data. ► Lessons learned from the natural convection test and the associated calculations are discussed. -- Abstract: The French Phenix sodium cooled fast reactor (SFR) started operation in 1973 and was stopped in 2009. Before the reactor was definitively shutdown, several final tests were planned and performed, including a natural convection test in the primary circuit. During this natural convection test, the heat rejection provided by the steam generators was disabled, followed several minutes later by reactor scram and coast-down of the primary pumps. The International Atomic Energy Agency (IAEA) launched a Coordinated Research Project (CRP) named “control rod withdrawal and sodium natural circulation tests performed during the Phenix end-of-life experiments”. The overall purpose of the CRP was to improve the Member States’ analytical capabilities in the field of SFR safety. An international benchmark on the natural convection test was organized with “blind” calculations in a first step, then “post-test” calculations and sensitivity studies compared with reactor measurements. Eight organizations from seven Member States took part in the benchmark: ANL (USA), CEA (France), IGCAR (India), IPPE (Russian Federation), IRSN (France), KAERI (Korea), PSI (Switzerland) and University of Fukui (Japan). Each organization performed computations and contributed to the analysis and global recommendations. This paper summarizes the findings of the CRP benchmark exercise associated with the Phenix natural convection test, including blind calculations, post-test calculations and comparisons with measured data. General comments and recommendations are pointed out to improve future simulations of natural convection in SFRs

  5. ["Dignity" at the end of life: ethical and deontologic reflections].

    Science.gov (United States)

    Mazzon, Davide

    2015-12-01

    Bioethical reflection is often raised to qualify medical treatment in relation to the concept of "dignity" of the human being. In philosophy, the concept of human dignity is used to refer to the intrinsic value of every human being but it has been framed in many different ways depending on the theoretical matrix we refer to. According to Christian principles, the dignity of human beings resides on their being created in the image and likeness of God: hence, the holiness of life for the believer and the condemnation of all means of action intended to anticipate death from suicide to euthanasia. On the contrary, according to the liberal tradition, human dignity is especially expressed in the autonomy of every human being. The Italian and the German Constitutions recall the value of human dignity. In the article 32 of the Italian Constitution, the concept of dignity is taken into account when stating the autonomy of the individual decision-making about health treatment. This is confirmed by the Code of Medical Ethics (2014): the right to self-determination and the right of patients to decide for themselves in accordance with their own life plans, are at the core of the concept of "human dignity". For this reason, doctors should support and encourage the full right of every patient to be considered as an autonomous person until the end of life, affirming his dignity. The acronym ABCD (airway, breathing, circulation, drugs) synthetises the essentials of intensive care procedures in life-threatening events. The same acronym should guide our behavior in promoting dignity in clinical settings. Attitude: moving away from our certainties, to better understand the real nature of the sick person we are approaching. Behavior: always be inspired by kindness and respect. Compassion, that is, deep awareness of the suffering, coupled with the desire to bring relief. Dialogue, being open to know the human being "behind" disease. This approach, developed by Chochinov and called

  6. Thermal-hydraulic codes validation for safety analysis of NPPs with RBMK

    International Nuclear Information System (INIS)

    Brus, N.A.; Ioussoupov, O.E.

    2000-01-01

    This work is devoted to validation of western thermal-hydraulic codes (RELAP5/MOD3 .2 and ATHLET 1.1 Cycle C) in application to Russian designed light water reactors. Such validation is needed due to features of RBMK reactor design and thermal-hydraulics in comparison with PWR and BWR reactors, for which these codes were developed and validated. These validation studies are concluded with a comparison of calculation results of modeling with the thermal-hydraulics codes with the experiments performed earlier using the thermal-hydraulics test facilities with the experimental data. (authors)

  7. Proceedings of the 8. Brazilian Meeting on Reactor Physics and Thermal Hydraulics

    International Nuclear Information System (INIS)

    1991-01-01

    Some papers about pressurized light water reactors, fast reactors, accident analysis, transients, research reactors, nuclear data collection, thermal hydraulics, reactor monitoring, neutronics are presented. (E.G.)

  8. Simulation of Phenix EOL Asymmetric Test

    Energy Technology Data Exchange (ETDEWEB)

    Ha, Kwi Seok; Lee, Kwi Lim; Choi, Chi Woong; Kang, Seok Hun; Chang, Won Pyo; Jeong, Hae Yong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2012-05-15

    The asymmetric test of End-Of-Life (EOL) tests on the Phenix plant was used for the evaluation of the MARS-LMR in the Generation IV frame as a part of the code validation. The purpose of the test is to evaluate the ability of the system code to describe asymmetric situations and to identify important phenomena during asymmetrical transient such as a three dimensional effect, buoyancy influence, and thermal stratification in the hot and cold pools. 3-dimensional sodium coolant mixing in the pools has different characteristics from the one dimensional full instantaneous mixing. The velocities and temperatures at the core outlet level differ at each sub-assembly and the temperature in the center of the hot pool may be high because the driver fuels are located at the center region. The temperatures in the hot pool are not the same in the radial and axial locations due to the buoyancy effect. The temperatures in the cold pool also differ along with the elevations and azimuthal directions due to the outlet location of IHX and the thermal stratification

  9. Worldwide end-of-life practice for patients in ICUs.

    Science.gov (United States)

    Wong, Wai-Tat; Phua, Jason; Joynt, Gavin M

    2018-04-01

    Published data and practice recommendations on end-of-life (EOL) generally reflect Western practice frameworks. Understanding worldwide practices is important because improving economic conditions are promoting rapid expansion of intensive care services in many previously disadvantaged regions, and increasing migration has promoted a new cultural diversity previously predominantly unicultural societies. This review explores current knowledge of similarities and differences in EOL practice between regions and possible causes and implications of these differences. Recent observational and survey data shows a marked variability in the practice of withholding and withdrawing life sustaining therapy worldwide. Some evidence supports the view that culture, religion, and socioeconomic factors influence EOL practice, and individually or together account for differences observed. There are also likely to be commonly desired values and expectations for EOL practice, and recent attempts at establishing where worldwide consensus may lie have improved our understanding of shared values and practices. Awareness of differences, understanding their likely complex causes, and using this knowledge to inform individualized care at EOL is likely to improve the quality of care for patients. Further research should clarify the causes of EOL practice variability, monitor trends, and objectively evaluate the quality of EOL practice worldwide.

  10. [Conscience clause in end-of-life care.

    Science.gov (United States)

    De Panfilis, Ludovica; Cattaneo, Daniela; Cola, Luisanna; Gasparini, Maddalena; Porteri, Corinna; Tarquini, Daniela; Tiezzi, Alessandro; Veronese, Simone; Zullo, Silvia; Pucci, Eugenio

    2017-05-01

    The article proposes a critical reflection on issues that appeal to the conscience clause as part of end of life care can produce and what can guarantee freedom of conscience, self-determination of those involved and respect for the dignity of the sick person. After a philosophical and normative analysis, the article is organized on the basis of two important documents for discussion: a position paper of Società Italiana di Anestesia Analgesia Rianimazione e Terapia Intensiva (SIAARTI) signed by several scientific societies "Grandi insufficienze d'organo end stage: cure intensive o cure palliative?" and the Design of Law currently being debated "Norme in materia di consenso informato e di disposizioni anticipate di trattamento". In particular, the conscience clause has been discussed in the light of advance care planning (ACP), which represents the instrument to guarantee the shared planning of care and the shared-decision making. In this context, recourse to the clause of conscience brings out critical ethical and deontological issues that the article discusses, using the position paper SIAARTI and the text of law currently being debated, both built on the assumptions of a shared care relationship, where patient has a key-role in medical decisions.

  11. Palliative sedation in end-of-life care.

    Science.gov (United States)

    Maltoni, Marco; Scarpi, Emanuela; Nanni, Oriana

    2013-07-01

    The aim of this review was to present and comment on recent data published on palliative sedation in palliative and end-of-life care. Palliative sedation is a medical procedure used to deal with the refractory symptoms occurring in the advanced stages of cancer. It has clinical, nursing, relational and ethical implications, making it a highly sensitive issue. Over the last 12 months, a number of authors have published interesting new findings on different areas of palliative sedation, that is prevalence, indications, monitoring, duration and choice of drugs. In particular, a clear definition of palliative sedation and of its more pronounced form, deep continuous sedation (DCS), has emerged. It has been confirmed that, when performed in the correct way and with the right aims, palliative sedation does not have a detrimental impact on survival. Recent findings confirm that palliative sedation is an integral part of a medical palliative care approach and is needed in certain clinical situations. It is a legitimate clinical practice from any ethical point of view. While oncologists should have a basic knowledge of the procedure, its in depth study is a core competency for palliative care physicians.

  12. Three factors critical for end-of-life care.

    Science.gov (United States)

    Franey, S G

    1996-01-01

    Appropriate care of persons with life-threatening illnesses requires a different, perhaps higher level of response from organized healthcare than has been typical in the past. This involves three critical components: Leaders must be committed, visible advocates of high-quality end-of-life care. This enables them to plan changes, deploy resources, and integrate this commitment throughout the organization's strategic plan. Ensuring appropriate care of the dying requires adequate human and financial resources. First, the organization must fully identify the educational and service needs of patients, families, and care givers experiencing life-threatening illnesses. The organization must work well with other community-based organizations to address identified needs. Senior managers can improve care by personally commissioning teams, acknowledging success, and rewarding performance. Finally, organizational goals, strategies, and performance objectives must be shaped by a commitment to ensure appropriate care of the dying. Our commitment to the dying must be based on our values. An organizational "statement of rights and responsibilities" is one way of providing a visible expression of the mission, core values, and mutual responsibilities among care givers and patients, residents, HMO members, and clients.

  13. Attitude Towards End of Life Communication of Austrian Medical Students.

    Science.gov (United States)

    Rumpold, Tamara; Lütgendorf-Caucig, Carola; Löffler-Stastka, Henriette; Roider-Schur, Sophie; Pötter, Richard; Kirchheiner, Kathrin

    2018-04-23

    Medical students have to acquire theoretical knowledge, practical skills, and a personal attitude to meet the emerging needs of palliative care. The present study aimed to assess the personal attitude of Austrian medical students towards end of life communication (EOLC), as key part of palliative care. This cross-sectional, mono-institutional assessment invited all medical students at the Medical University of Vienna in 2015. The assessment was conducted web-based via questionnaire about attitudes towards EOLC. Additional socio-demographic and medical education-related parameters were collected. Overall, 743 medical students participated in the present report. Differences regarding the agreement or disagreement to several statements concerning the satisfaction of working with chronically ill patients, palliative care, and health care costs, as well as the extent of information about palliative disease, were found for age, gender, and academic years. The overall attitude towards EOLC in the present sample can be regarded as quite balanced. Nevertheless, a considerable number of medical students are still reluctant to inform patients about their incurable disease. Reservations towards palliative care as part of the health care system seem to exist. The influence of the curriculum as well as practical experiences seems to be important but needs further investigation.

  14. Hospital end-of-life care in haematological malignancies.

    Science.gov (United States)

    Beaussant, Yvan; Daguindau, Etienne; Chauchet, Adrien; Rochigneux, Philippe; Tournigand, Christophe; Aubry, Régis; Morin, Lucas

    2018-02-06

    To investigate patterns of care during the last months of life of hospitalised patients who died from different haematological malignancies. Nationwide register-based study, including all hospitalised adults ≥20 years who died from haematological malignancies in France in 2010-2013. Outcomes included use of invasive cancer treatments and referral to palliative care. Percentages are adjusted for sex and age using direct standardisation. Of 46 629 inpatients who died with haematological malignancies, 24.5% received chemotherapy during the last month before death, 48.5% received blood transfusion, 12.3% were under invasive ventilation and 18.1% died in intensive care units. We found important variations between haematological malignancies. The use of chemotherapy during the last month of life varied from 8.6% among patients with chronic myeloid leukaemia up to 30.1% among those with non-Hodgkin's lymphoma (Pcare units. A high proportion of patients who died from haematological malignancies receive specific treatments near the end of life. There is a need for a better and earlier integration of the palliative care approach in the standard practice of haematology. However, substantial variation according to the type of haematological malignancy suggests that the patients should not be considered as one homogeneous group. Implementation of palliative care should account for differences across haematological malignancies. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  15. End-of-life decision making is more than rational.

    Science.gov (United States)

    Eliott, Jaklin A; Olver, Ian N

    2005-01-01

    Most medical models of end-of-life decision making by patients assume a rational autonomous adult obtaining and deliberating over information to arrive at some conclusion. If the patient is deemed incapable of this, family members are often nominated as substitutes, with assumptions that the family are united and rational. These are problematic assumptions. We interviewed 23 outpatients with cancer about the decision not to resuscitate a patient following cardiopulmonary arrest and examined their accounts of decision making using discourse analytical techniques. Our analysis suggests that participants access two different interpretative repertoires regarding the construct of persons, invoking a 'modernist' repertoire to assert the appropriateness of someone, a patient or family, making a decision, and a 'romanticist' repertoire when identifying either a patient or family as ineligible to make the decision. In determining the appropriateness of an individual to make decisions, participants informally apply 'Sanity' and 'Stability' tests, assessing both an inherent ability to reason (modernist repertoire) and the presence of emotion (romanticist repertoire) which might impact on the decision making process. Failure to pass the tests respectively excludes or excuses individuals from decision making. The absence of the romanticist repertoire in dominant models of patient decision making has ethical implications for policy makers and medical practitioners dealing with dying patients and their families.

  16. Transitioning from interpretive to predictive in thermal hydraulic codes

    International Nuclear Information System (INIS)

    Mousseau, V.A.

    2004-01-01

    The current thermal hydraulic codes in use in the US, RELAP and TRAC, where originally written in the mid to late 1970's. At that time computers were slow, expensive, and had small memories. Because of these constraints, sacrifices had to be made, both in physics and numerical methods, which resulted in limitations on the accuracy of the solutions. Significant changes have occurred that induce very different requirements for the thermal hydraulic codes to be used for the future GEN-IV nuclear reactors. First, computers speed and memory grow at an exponential rate while the costs hold constant or decrease. Second, passive safety systems in modern designs stretch the length of relevant transients to many days. Finally, costs of experiments have grown very rapidly. Because of these new constraints, modern thermal hydraulic codes will be relied on for a significantly larger portion of bringing a nuclear reactor on line. Simulation codes will have to define in which part of state space experiments will be run. They will then have to be able to extend the small number of experiments to cover the large state space in which the reactors will operate. This data extrapolation mode will be referred to as 'predictive'. One of the keys to analyzing the accuracy of a simulation is to consider the entire domain being simulated. For example, in a reactor design where the containment is coupled to the reactor cooling system through radiative heat transfer, the accuracy of a transient includes the containment, the radiation heat transfer, the fluid flow in the cooling system, the thermal conduction in the solid, and the neutron transport in the reactor. All of this physics is coupled together in one nonlinear system through material properties, cross sections, heat transfer coefficients, and other mechanisms that exchange mass, momentum, and energy. Traditionally, these different physical domains, (containment, cooling system, nuclear fuel, etc.) have been solved in different

  17. Validation of containment thermal hydraulic computer codes for VVER reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jiri Macek; Lubomir Denk [Nuclear Research Institute Rez plc Thermal-Hydraulic Analyses Department CZ 250 68 Husinec-Rez (Czech Republic)

    2005-07-01

    Full text of publication follows: The Czech Republic operates 4 VVER-440 units, two VVER-1000 units are being finalized (one of them is undergoing commissioning). Thermal-hydraulics Department of the Nuclear Research Institute Rez performs accident analyses for these plants using a number of computer codes. To model the primary and secondary circuits behaviour the system codes ATHLET, CATHARE, RELAP, TRAC are applied. Containment and pressure-suppression system are modelled with COCOSYS and MELCOR codes, the reactor power calculations (point and space-neutron kinetics) are made with DYN3D, NESTLE and CDF codes (FLUENT, TRIO) are used for some specific problems.An integral part of the current Czech project 'New Energy Sources' is selection of a new nuclear source. Within this and the preceding projects financed by the Czech Ministry of Industry and Trade and the EU PHARE, the Department carries and has carried out the systematic validation of thermal-hydraulic and reactor physics computer codes applying data obtained on several experimental facilities as well as the real operational data. One of the important components of the VVER 440/213 NPP is its containment with pressure suppression system (bubble condenser). For safety analyses of this system, computer codes of the type MELCOR and COCOSYS are used in the Czech Republic. These codes were developed for containments of classic PWRs or BWRs. In order to apply these codes for VVER 440 systems, their validation on experimental facilities must be performed.The paper provides concise information on these activities of the NRI and its Thermal-hydraulics Department. The containment system of the VVER 440/213, its functions and approaches to solution of its safety is described with definition of acceptance criteria. A detailed example of the containment code validation on EREC Test facility (LOCA and MSLB) and the consequent utilisation of the results for a real NPP purposes is included. An approach to

  18. Emotional Numbness Modifies the Effect of End-of-Life Discussions on End-of-Life Care

    Science.gov (United States)

    Maciejewski, Paul K.; Prigerson, Holly G.

    2012-01-01

    Context Overall, end-of-life (EOL) discussions are unrelated to psychological distress and associated with lower rates of aggressive care near death. Nevertheless, patients who report they feel emotionally numb about their illness might encounter difficulties cognitively processing an EOL discussion. Objectives We hypothesized that emotional numbness would modify the influence of EOL discussions on the receipt of less aggressive EOL care. Methods Data were derived from structured interviews with 290 participants in the federally-funded Coping with Cancer Study, a multisite, prospective cohort study of advanced cancer patients followed through their death. Patients’ reports of EOL discussions with their physician and emotional numbness were assessed a median of 4.6 months before death. Information about aggressive EOL care (i.e., ventilation, resuscitation in the last week of life, death in the Intensive Care Unit) was obtained from postmortem caregiver interviews and medical charts. Main and interactive effects of EOL discussions and emotional numbness on aggressive EOL care, adjusting for potential confounds, were evaluated using multiple logistic regression. Results The likelihood of aggressive EOL care associated with having EOL discussions increased by a factor of nine (adjusted odds ratio=9.02, 95% confidence interval 1.37, 59.6, P=0.022) for every unit increase in a patient’s emotional numbness score. Conclusion Emotional numbness diminishes a patient’s capacity to benefit from EOL discussions. EOL decision making may be more effective if clinical communications with emotionally numb patients are avoided. PMID:22926093

  19. Thermal-hydraulics associated with nuclear education and research

    International Nuclear Information System (INIS)

    Yokobori, Seiichi

    2011-01-01

    This article was the rerecording of the author's lecture at the fourth 'Future Energy Forum' (aiming at improving nuclear safety and economics) held in December 2010. The lecture focused on (1) importance of thermal hydraulics associated with nuclear education and research (critical heat flux, two-phase flow and multiphase flow), (2) emerging trend of maintenance engineering (fluid induced vibration, flow accelerated corrosion and stress corrosion cracks), (3) fostering sensible nuclear engineer with common engineering sense, (4) balanced curriculum of basics and advanced research, (5) computerized simulation and fluid mechanics, (6) crucial point of thermo hydraulics education (viscosity, flux, steam and power generation), (7) safety education and human resources development (indispensable technologies such as defence in depth) and (8) topics of thermo hydraulics research (vortices of curbed pipes and visualization of two-phase flow). (T. Tanaka)

  20. Evolution of thermal-hydraulics testing in EBR-II

    International Nuclear Information System (INIS)

    Golden, G.H.; Planchon, H.P.; Sackett, J.I.; Singer, R.M.

    1987-01-01

    A thermal-hydraulics testing and modeling program has been underway at the Experimental Breeder Reactor-II (EBR-II) for 12 years. This work culminated in two tests of historical importance to commercial nuclear power, a loss of flow without scram and a loss of heat sink wihout scram, both from 100% initial power. These tests showed that natural processes will shut EBR-II down and maintain cooling without automatic control rod action or operator intervention. Supporting analyses indicate that these results are characteristic of a range of sizes of liquid metal cooled reactors (LMRs), if these reactors use metal driver fuel. This type of fuel is being developed as part of the Integral Fast Reactor Program at Argonne National Laboratory. Work is now underway at EBR-II to exploit the inherent safety of metal-fueled LMRs with regard to development of improved plant control strategies. (orig.)

  1. submitter Thermal, Hydraulic, and Electromagnetic Modeling of Superconducting Magnet Systems

    CERN Document Server

    Bottura, L

    2016-01-01

    Modeling techniques and tailored computational tools are becoming increasingly relevant to the design and analysis of large-scale superconducting magnet systems. Efficient and reliable tools are useful to provide an optimal forecast of the envelope of operating conditions and margins, which are difficult to test even when a prototype is available. This knowledge can be used to considerably reduce the design margins of the system, and thus the overall cost, or increase reliability during operation. An integrated analysis of a superconducting magnet system is, however, a complex matter, governed by very diverse physics. This paper reviews the wide spectrum of phenomena and provides an estimate of the time scales of thermal, hydraulic, and electromagnetic mechanisms affecting the performance of superconducting magnet systems. The analysis is useful to provide guidelines on how to divide the complex problem into building blocks that can be integrated in a design and analysis framework for a consistent multiphysic...

  2. Thermal hydraulic stability in a pressure tube nuclear reactor

    International Nuclear Information System (INIS)

    Villani, A.; Ravetta, R.; Mansani, L.

    1986-01-01

    The CIRENE plant which will undergo preoperational tests in the near future is equipped with a 40 MW(e) Heavy Water moderated Boiling Light Water cooled Reactor (HWBLWR); at the start-up and up to about 30 % of nominal power, the necessary low coolant density is obtained injecting into the core a mixture of liquid and steam. To verify the thermal-hydraulic stability of the plant in this situation, tests have been carried out in a facility simulating two full scale power channels; the system stability has been confirmed in the reference conditions, and is not reduced by even a significant reduction of the liquid flowrate, where a decrease in liquid temperature has some negative effect and steam flowrate has a small influence. (author)

  3. GNPS 18-months fuel cycles core thermal hydraulic design

    International Nuclear Information System (INIS)

    Liu Changwen; Zhou Zhou

    2002-01-01

    GNPS begins to implement the 18-month fuel cycles from the initial annual reload at cycle 9, thus the initial core thermal hydraulic design is not valid any more. The new critical heat flux (CHF) correlation, FC, which is developed by Framatome, is used in the design, and the generalized statistical methodology (GSM) instead of the initial deterministic methodology is used to determine the DNBR design limit. As the AFA 2G and AFA 3G are mixed loaded in the transition cycle, it will result that the minimum DNBR in the mixed core is less than that of AFA 3G homogenous core, the envelop mixed core DNBR penalty is given. Consequently the core physical limit for mixed core and equilibrium cycles, and the new over temperature ΔT overpower ΔT are determined

  4. Report on the thermal-hydraulics computational component

    International Nuclear Information System (INIS)

    Laughton, T.; Jones, B.G.

    1996-01-01

    The nodal methods computer code utilizing hexagonal geometry, which is being developed as part of this DOE contract, is called THMZ. The computational objective of the code is to calculate the steady-state thermal-hydraulic conditions in a hexagonal geometry reactor core given the appropriate initial conditions and the axial neutron flux profile. The latter is given by a companion nodal neutronics code which was developed in an earlier part of the contact. The joining of these two codes to provide a coupled analysis tool for hexagonal lattice cores is the ultimate objective of the contract and its follow-on work. The remaining part of this report presents the current status of the development and the results which have been obtained to date. These will appear in the MS thesis of Mr. Terrill Laughton in the Department of Nuclear Engineering which is currently in preparation

  5. Thermal hydraulic evaluation of advanced wire-wrapped assemblies

    International Nuclear Information System (INIS)

    Wei, J.P.

    1975-01-01

    The thermal-hydraulic analyses presented in this report are based on application of the subchannel concept in association with the use of bulk parameters for coolant velocity and coolant temperature within a subchannel. The interactions between subchannels are due to turbulent interchange, pressure-induced diversion crossflow, directed sweeping crossflow induced by the helical wire wrap, and transverse thermal conduction. The FULMIX-II computer program was successfully developed to perform the steady-state temperature predictions for LMFBR fuel assemblies with the reference straight-start design and the advanced wire-wrap designs. Predicted steady-state temperature profiles are presented for a typical CRBRP 217-rod wire-wrapped assembly with the selected wire-wrap designs

  6. Spent nuclear fuel storage pool thermal-hydraulic analysis

    International Nuclear Information System (INIS)

    Gay, R.R.

    1984-01-01

    Storage methods and requirements for spent nuclear fuel at U.S. commercial light water reactors are reviewed in Section 1. Methods of increasing current at-reactor storage capabilities are also outlined. In Section 2 the development of analytical methods for the thermal-hydraulic analysis of spent fuel pools is chronicled, leading up to a discussion of the GFLOW code which is described in Section 3. In Section 4 the verification of GFLOW by comparisons of the code's predictions to experimental data taken inside the fuel storage pool at the Maine Yankee nuclear power plant is presented. The predictions of GFLOW using 72, 224, and 1584 node models of the storage pool are compared to each other and to the experimental data. An example of thermal licensing analysis for Maine Yankee using the GFLOW code is given in Section 5. The GFLOW licensing analysis is compared to previous licensing analysis performed by Yankee Atomic using the RELAP-4 computer code

  7. Thermal hydraulic analysis of the encapsulated nuclear heat source

    Energy Technology Data Exchange (ETDEWEB)

    Sienicki, J.J.; Wade, D.C. [Argonne National Lab., IL (United States)

    2001-07-01

    An analysis has been carried out of the steady state thermal hydraulic performance of the Encapsulated Nuclear Heat Source (ENHS) 125 MWt, heavy liquid metal coolant (HLMC) reactor concept at nominal operating power and shutdown decay heat levels. The analysis includes the development and application of correlation-type analytical solutions based upon first principles modeling of the ENHS concept that encompass both pure as well as gas injection augmented natural circulation conditions, and primary-to-intermediate coolant heat transfer. The results indicate that natural circulation of the primary coolant is effective in removing heat from the core and transferring it to the intermediate coolant without the attainment of excessive coolant temperatures. (authors)

  8. Validation of the TEXSAN thermal-hydraulic analysis program

    International Nuclear Information System (INIS)

    Burns, S.P.; Klein, D.E.

    1992-01-01

    The TEXSAN thermal-hydraulic analysis program has been developed by the University of Texas at Austin (UT) to simulate buoyancy driven fluid flow and heat transfer in spent fuel and high level nuclear waste (HLW) shipping applications. As part of the TEXSAN software quality assurance program, the software has been subjected to a series of test cases intended to validate its capabilities. The validation tests include many physical phenomena which arise in spent fuel and HLW shipping applications. This paper describes some of the principal results of the TEXSAN validation tests and compares them to solutions available in the open literature. The TEXSAN validation effort has shown that the TEXSAN program is stable and consistent under a range of operating conditions and provides accuracy comparable with other heat transfer programs and evaluation techniques. The modeling capabilities and the interactive user interface employed by the TEXSAN program should make it a useful tool in HLW transportation analysis

  9. Consequences count: against absolutism at the end of life.

    Science.gov (United States)

    Snelling, Paul C

    2004-05-01

    There has been a considerable amount of debate in the nursing literature about euthanasia, and especially the distinctions between acts and omissions, and killing and letting die. These distinctions are required by opponents of euthanasia to justify allowing some cases of passive euthanasia while forbidding all cases of active euthanasia. This paper adds to the debate by arguing that the position that absolutely forbids euthanasia is theoretically inconsistent. The paper first considers the place of moral theory in analysing moral problems, within the framework of the principles of biomedical ethics. It is argued that despite a moral pluralism that operates in many areas, the legal status of euthanasia is based upon an absolute deontological position against deliberate killing, which cannot be overridden by appeals to favourable consequences. In order that certain forms of passive euthanasia can be allowed, this position allows distinctions within three pairs of concepts--acts and omissions, killing and letting die, and ordinary and extraordinary means. A further method of justifying certain actions near the end of life is the doctrine of double effect. These paired concepts and the doctrine of double effect are analysed with special reference to their consequences. The application of the doctrine of double effect and the three distinctions relies on consideration of their consequences, allowing in practice what in theory is denied. This is important because it weakens the absolute case against euthanasia, which disallows any direct consequentialist appeal. If consequences count in the application of the doctrine and the distinctions, then they should also count directly prior to their application. This strengthens the argument for active euthanasia in certain cases.

  10. Fatigue in children with cancer at the end of life.

    Science.gov (United States)

    Ullrich, Christina K; Dussel, Veronica; Hilden, Joanne M; Sheaffer, Jan W; Moore, Caron L; Berde, Charles B; Wolfe, Joanne

    2010-10-01

    Fatigue is a prevalent source of suffering in children with advanced cancer; yet, little is known about it. This study aimed to describe fatigue experienced by children with advanced cancer and to identify the factors associated with suffering from fatigue and its treatment. A retrospective cross-sectional study of 141 parents of children who died of cancer (response rate: 64%) was conducted in two tertiary-level U.S. pediatric hospitals. By parent report, 96% of children experienced fatigue in the last month of life. Nearly 50% experienced significant suffering from fatigue; this was associated with suffering from pain, dyspnea, anorexia, nausea/vomiting, diarrhea, anxiety, sadness, or fear (Pfear (OR=5.13, 95% CI=2.03-12.96, P ≤ 0.001) remained independently associated with fatigue. Children suffering from fatigue had primary oncologists with fewer years' experience than children who did not suffer from fatigue (mean=7.7 years, standard deviation [SD]=4.9 vs. mean of 9.9 years, SD=6.0, P=0.02). Among children with fatigue, 17 of 129 (13%) received fatigue-directed treatment, which was successful in 3 of 12 (25%). Children experiencing side effects from dyspnea or pain treatment were more likely to be treated for fatigue (relative risk=1.25, 95% CI=1.06-1.47, P=0.009). Fatigue is a common source of suffering in children with cancer at the end of life. Palliation of this symptom is rarely successful. Increased attention to factors associated with fatigue and effective interventions to ameliorate fatigue are needed. Copyright © 2010 U.S. Cancer Pain Relief Committee. Published by Elsevier Inc. All rights reserved.

  11. Homeless Individuals Approaching the End of Life: Symptoms and Attitudes.

    Science.gov (United States)

    Tobey, Matthew; Manasson, Julia; Decarlo, Kristen; Ciraldo-Maryniuk, Katrina; Gaeta, Jessie M; Wilson, Erica

    2017-04-01

    Over a million individuals in the United States experience homelessness annually and homeless individuals die at a higher rate than domiciled peers. Homeless individuals often have unique experiences at the end of life (EOL). This study examined the symptoms experienced by homeless individuals nearing the EOL and explored social background, attitudes, and experiences. Investigators conducted surveys of homeless individuals approaching the EOL at a medical respite home. Eligibility required a serious medical condition and for the patient's medical provider to answer "no" to the question "Would you be surprised if this patient were not alive in one year?" Interviews explored symptoms using the Memorial Symptom Assessment Survey. Symptoms were compared with those of relevant comparator groups in other studies. Participants (n = 20) were young to face the EOL (median age = 58) and suffered high rates of substance use disorders (n = 18; 90%) and psychiatric diagnoses (n = 16; 80%). Symptom frequency was high, especially as regarded pain and psychological symptoms. Previous experience with death among family and peers was universal (n = 20; 100%). Mistrust of others' decisions about the EOL was common, as was concern about receiving too little (n = 11; 55%) or too much (n = 8; 40%) care at the EOL. The frequency of symptoms was higher than in three comparator studies and those studies' subgroups (P Homeless individuals may experience a high frequency of pain and other symptoms as they approach the EOL. Care for such individuals may require a tailored approach. Copyright © 2017 American Academy of Hospice and Palliative Medicine. Published by Elsevier Inc. All rights reserved.

  12. Ethical decision-making near the end of life.

    Science.gov (United States)

    Finucane, T E; Harper, M

    1996-05-01

    For ethical decision-making near the end of life, autonomy is the moral North Star. At the same time, for some treatments, the burdens so clearly outweigh benefits that physicians may make a judgment not to offer the treatment. This is often clearer in surgery. A person with colon cancer and metastases may not insist on resection of the metastases. For some reason, some treatments have escaped these logical constraints. Attempted resuscitation of a dying patient is a good example. The circumstances in which a physician may make choices on behalf of a competent, terminally-ill patient without consent, and even without notification, are hotly debated, but data suggest that physicians do so frequently. Patients who lack capacity present even more difficult challenges. Advance directives, when available, can be extremely helpful, but even with them difficult problems can remain. If advance directives have not been established, family and close friends are an obvious source of guidance. Their legal role varies in different jurisdictions; in practice, they are crucial in bedside decision-making. Guardianship and alternatives to it remain a poor last resort. Euthanasia is a very difficult problem. We believe it is semantically misleading to lump under the term "passive euthanasia" those circumstances where potentially life-sustaining treatment is withheld or withdrawn. The tension between patient autonomy and medical common sense remains unresolved within the "futility" controversy. The authors believe it serves no purpose to discuss carefully with dying patients propositions that are nonsense. At the same time, physicians must not confuse decisions about quality of life with judgements about treatment effectiveness. We believe that what many, although not all, dying patients want are physicians with intelligent compassion who can take care of them through the dying process.

  13. Engaging homeless persons in end of life preparations.

    Science.gov (United States)

    Song, John; Wall, Melanie M; Ratner, Edward R; Bartels, Dianne M; Ulvestad, Nancy; Gelberg, Lillian

    2008-12-01

    There are no prospective studies that have investigated the effects of an intervention to improve end of life (EOL) care in an underserved population. To determine whether homeless persons will complete an advance directive (AD). Randomized trial comparing two modes of providing an opportunity for homeless persons to complete an AD. Half of the subjects were randomized to a self-guided group (SG) who were given an AD and written instructions; the other half were given the same material but, in addition, were offered the opportunity to receive guidance to complete the AD (CG). Fifty-nine homeless persons recruited from a drop-in center. Rate of AD completion and baseline and 3-month follow-up EOL-related knowledge, attitudes, and behaviors. The overall AD completion rate was 44%, with a statistically significant higher completion rate of 59% in the CG group compared to 30% in the self-guided only group. Frequency of worry about death decreased among those who filled out an AD from 50% to 12.5%, and also among those who did not (25% to 12.5%) (p < .05). Among those who filled out an AD, there were increases in plans to write down EOL wishes (56% to 100%; p < .05) and plans to talk about these wishes with someone (63% to 94%; p < .05). This study demonstrates that people living in dire economic and social situations will complete an AD when offered the opportunity. While offering guidance resulted in higher rates of completion; even a simple self-guided AD process can achieve completion of ADs in this population.

  14. End-of-life care in pediatric neuro-oncology.

    Science.gov (United States)

    Vallero, Stefano Gabriele; Lijoi, Stefano; Bertin, Daniele; Pittana, Laura Stefania; Bellini, Simona; Rossi, Francesca; Peretta, Paola; Basso, Maria Eleonora; Fagioli, Franca

    2014-11-01

    The management of children with cancer during the end-of-life (EOL) period is often difficult and requires skilled medical professionals. Patients with tumors of the central nervous system (CNS) with relapse or disease progression might have additional needs because of the presence of unique issues, such as neurological impairment and altered consciousness. Very few reports specifically concerning the EOL period in pediatric neuro-oncology are available. Among all patients followed at our center during the EOL, we retrospectively analyzed data from 39 children and adolescents with brain tumors, in order to point out on their peculiar needs. Patients were followed-up for a median time of 20.1 months. Eighty-two percent were receiving only palliative therapy before death. Almost half the patients (44%) died at home, while 56% died in a hospital. Palliative sedation with midazolam was performed in 58% of cases; morphine was administered in 51.6% of cases. No patient had uncontrolled pain. The EOL in children with advanced CNS cancer is a period of active medical care. Patients may develop complex neurological symptoms and often require long hospitalization. We organized a network-based collaboration among the reference pediatric oncology center, other pediatric hospitals and domiciliary care personnel, with the aim to ameliorate the quality of care during the EOL period. In our cohort, palliative sedation was widely used while no patients died with uncontrolled pain. A precise process of data collection and a better sharing of knowledge are necessary in order to improve the management of such patients. © 2014 Wiley Periodicals, Inc.

  15. End-of-life flows of multiple cycle consumer products

    International Nuclear Information System (INIS)

    Tsiliyannis, C.A.

    2011-01-01

    Explicit expressions for the end-of-life flows (EOL) of single and multiple cycle products (MCPs) are presented, including deterministic and stochastic EOL exit. The expressions are given in terms of the physical parameters (maximum lifetime, T, annual cycling frequency, f, number of cycles, N, and early discard or usage loss). EOL flows are also obtained for hi-tech products, which are rapidly renewed and thus may not attain steady state (e.g. electronic products, passenger cars). A ten-step recursive procedure for obtaining the dynamic EOL flow evolution is proposed. Applications of the EOL expressions and the ten-step procedure are given for electric household appliances, industrial machinery, tyres, vehicles and buildings, both for deterministic and stochastic EOL exit, (normal, Weibull and uniform exit distributions). The effect of the physical parameters and the stochastic characteristics on the EOL flow is investigated in the examples: it is shown that the EOL flow profile is determined primarily by the early discard dynamics; it also depends strongly on longevity and cycling frequency: higher lifetime or early discard/loss imply lower dynamic and steady state EOL flows. The stochastic exit shapes the overall EOL dynamic profile: Under symmetric EOL exit distribution, as the variance of the distribution increases (uniform to normal to deterministic) the initial EOL flow rise becomes steeper but the steady state or maximum EOL flow level is lower. The steepest EOL flow profile, featuring the highest steady state or maximum level, as well, corresponds to skew, earlier shifted EOL exit (e.g. Weibull). Since the EOL flow of returned products consists the sink of the reuse/remanufacturing cycle (sink to recycle) the results may be used in closed loop product lifecycle management operations for scheduling and sizing reverse manufacturing and for planning recycle logistics. Decoupling and quantification of both the full age EOL and of the early discard flows is

  16. Scaling in nuclear reactor system thermal-hydraulics

    International Nuclear Information System (INIS)

    D'Auria, F.; Galassi, G.M.

    2010-01-01

    Scaling is a reference 'key-word' in engineering and in physics. The relevance of scaling in the water cooled nuclear reactor technology constitutes the motivation for the present paper. The origin of the scaling-issue, i.e. the impossibility to get access to measured data in case of accident in nuclear reactors, is discussed at first. The so-called 'scaling-controversy' constitutes an outcome. Then, a critical survey (or 'scaling state-of-art';) is given of the attempts and of the approaches to provide a solution to the scaling-issue in the area of Nuclear Reactor System Thermal-Hydraulics (NRSTH): dimensionless design factors for Integral Test Facilities (ITF) are distinguished from scaling factors. The last part of the paper has a two-fold nature: (a) classifying the information about achievements in the area of thermal-hydraulics which are relevant to scaling: the concepts of 'scaling-pyramid' and the related 'scaling bridges' are introduced; (b) establishing a logical path across the scaling achievements (represented as a 'scaling puzzle'). In this context, the 'roadmap for scaling' is proposed: the objective is addressing the scaling issue when demonstrating the applicability of system codes in the licensing process of nuclear power plants. The code itself is referred hereafter as the 'key-to-scaling'. The database from the operation of properly scaled ITF and the availability of qualified system codes are identified as main achievements in NRSTH connected with scaling. The 'roadmap to scaling' constitutes a unified approach to scaling which aims at solving the 'scaling puzzle' created by researches performed during a half-a-century period.

  17. Scaling in nuclear reactor system thermal-hydraulics

    Energy Technology Data Exchange (ETDEWEB)

    D' Auria, F., E-mail: dauria@ing.unipi.i [Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, University of Pisa, Via Diotisalvi 2, 56126 Pisa (Italy); Galassi, G.M. [Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, University of Pisa, Via Diotisalvi 2, 56126 Pisa (Italy)

    2010-10-15

    Scaling is a reference 'key-word' in engineering and in physics. The relevance of scaling in the water cooled nuclear reactor technology constitutes the motivation for the present paper. The origin of the scaling-issue, i.e. the impossibility to get access to measured data in case of accident in nuclear reactors, is discussed at first. The so-called 'scaling-controversy' constitutes an outcome. Then, a critical survey (or 'scaling state-of-art';) is given of the attempts and of the approaches to provide a solution to the scaling-issue in the area of Nuclear Reactor System Thermal-Hydraulics (NRSTH): dimensionless design factors for Integral Test Facilities (ITF) are distinguished from scaling factors. The last part of the paper has a two-fold nature: (a) classifying the information about achievements in the area of thermal-hydraulics which are relevant to scaling: the concepts of 'scaling-pyramid' and the related 'scaling bridges' are introduced; (b) establishing a logical path across the scaling achievements (represented as a 'scaling puzzle'). In this context, the 'roadmap for scaling' is proposed: the objective is addressing the scaling issue when demonstrating the applicability of system codes in the licensing process of nuclear power plants. The code itself is referred hereafter as the 'key-to-scaling'. The database from the operation of properly scaled ITF and the availability of qualified system codes are identified as main achievements in NRSTH connected with scaling. The 'roadmap to scaling' constitutes a unified approach to scaling which aims at solving the 'scaling puzzle' created by researches performed during a half-a-century period.

  18. COOLOD, Steady-State Thermal Hydraulics of Research Reactors

    International Nuclear Information System (INIS)

    Kaminaga, Masanori

    1997-01-01

    1 - Description of program or function: The COOLOD-N2 code provides a capability for the analyses of the steady-state thermal-hydraulics of research reactors. This code is a revised version of the COOLOD-N code, and is applicable not only for research reactors in which plate-type fuel is adopted, but also for research reactors in which rod-type fuel is adopted. In the code, subroutines to calculate temperature distribution in rod-type fuel have been newly added to the COOLOD-N code. The COOLOD-N2 code can calculate fuel temperatures under both forced convection cooling mode and natural convection cooling mode. A 'Heat Transfer package' is used for calculating heat transfer coefficient, DNB heat flux etc. The 'Heat Transfer package' is a subroutine program and is especially developed for research reactors in which plate-type fuel is adopted. In case of rod-type fuel, DNB heat flux is calculated by both the 'Heat Transfer package' and Lund DNB heat flux correlation which is popular for TRIGA reactor. The COOLOD-N2 code also has a capability of calculating ONB temperature, the heat flux at onset of flow instability as well as DNB heat flux. 2 - Method of solution: The 'Heat Transfer Package' is a subprogram for calculating heat transfer coefficients, ONB temperature, heat flux at onset of flow instability and DNB heat flux. The 'Heat transfer package' was especially developed for research reactors which are operated under low pressure and low temperature conditions using plate-type fuel, just like the JRR-3M. Heat transfer correlations adopted in the 'Heat Transfer Package' were obtained or estimated based on the heat transfer experiments in which thermal-hydraulic features of the upgraded JRR-3 core were properly reflected. The 'Heat Transfer Package' is applicable to upward and downward flow

  19. ATLAS program for advanced thermal-hydraulic safety research

    International Nuclear Information System (INIS)

    Song, Chul-Hwa; Choi, Ki-Yong; Kang, Kyoung-Ho

    2015-01-01

    Highlights: • Major achievements of the ATLAS program are highlighted in conjunction with both developing advanced light water reactor technologies and enhancing the nuclear safety. • The ATLAS data was shown to be useful for the development and licensing of new reactors and safety analysis codes, and also for nuclear safety enhancement through domestic and international cooperative programs. • A future plan for the ATLAS testing is introduced, covering recently emerging safety issues and some generic thermal-hydraulic concerns. - Abstract: This paper highlights the major achievements of the ATLAS program, which is an integral effect test program for both developing advanced light water reactor technologies and contributing to enhancing nuclear safety. The ATLAS program is closely related with the development of the APR1400 and APR"+ reactors, and the SPACE code, which is a best-estimate system-scale code for a safety analysis of nuclear reactors. The multiple roles of ATLAS testing are emphasized in very close conjunction with the development, licensing, and commercial deployment of these reactors and their safety analysis codes. The role of ATLAS for nuclear safety enhancement is also introduced by taking some examples of its contributions to voluntarily lead to multi-body cooperative programs such as domestic and international standard problems. Finally, a future plan for the utilization of ATLAS testing is introduced, which aims at tackling recently emerging safety issues such as a prolonged station blackout accident and medium-size break LOCA, and some generic thermal-hydraulic concerns as to how to figure out multi-dimensional phenomena and the scaling issue.

  20. Study on thermal-hydraulics during a PWR reflood phase

    Energy Technology Data Exchange (ETDEWEB)

    Iguchi, Tadashi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-10-01

    In-core thermal-hydraulics during a PWR reflood phase following a large-break LOCA are quite unique in comparison with two-phase flow which has been studied widely in previous researches, because the geometry of the flow path is complicated (bundle geometry) and water is at extremely low superficial velocity and almost under stagnant condition. Hence, some phenomena realized during a PWR reflood phase are not understood enough and appropriate analytical models have not been developed, although they are important in a viewpoint of reactor safety evaluation. Therefore, author investigated some phenomena specified as important issues for quantitative prediction, i.e. (1) void fraction in a bundle during a PWR reflood phase, (2) effect of radial core power profile on reflood behavior, (3) effect of combined emergency core coolant injection on reflood behavior, and (4) the core separation into two thermal-hydraulically different regions and the in-core flow circulation behavior observed during a combined injection PWR reflood phase. Further, author made analytical models for these specified issues, and succeeded to predict reflood behaviors at representative types of PWRs, i.e.cold leg injection PWRs and Combined injection PWRs, in good accuracy. Above results were incorporated into REFLA code which is developed at JAERI, and they improved accuracy in prediction and enlarged applicability of the code. In the present study, models were intended to be utilized in a practical use, and hence these models are simplified ones. However, physical understanding on the specified issues in the present study is basic and principal for reflood behavior, and then it is considered to be used in a future advanced code development and improvement. (author). 110 refs.

  1. A model for emergency department end-of-life communications after acute devastating events--part II: moving from resuscitative to end-of-life or palliative treatment.

    Science.gov (United States)

    Limehouse, Walter E; Feeser, V Ramana; Bookman, Kelly J; Derse, Arthur

    2012-11-01

    The model for emergency department (ED) end-of-life communications after acute devastating events addresses decision-making capacity, surrogates, and advance directives, including legal definitions and application of these steps. Part II concerns communications moving from resuscitative to palliative and end-of-life treatments. After completing the steps involved in determining decision-making, emergency physicians (EPs) should consider starting palliative measures versus continuing resuscitative treatment. As communications related to these end-of-life decisions increasingly fall within the scope of emergency medicine (EM) practice, we need to become educated about and comfortable with them. © 2012 by the Society for Academic Emergency Medicine.

  2. Study on the thermal-hydraulic stability of high burn up STEP III fuel in Japan

    International Nuclear Information System (INIS)

    Ishikawa, M.; Kitamura, H.; Toba, A.; Omoto, A.

    2004-01-01

    Japanese BWR utilities have performed a joint study of the Thermal Hydraulic Stability of High Burn up STEP III Fuel. In this study, the parametric dependency of thermal hydraulic stability threshold was obtained. It was confirmed through experiments that the STEP III Fuel has sufficient stability characteristics. (author)

  3. Preliminary thermal/hydraulic sizing calculations for duplex tube evaporator/superheater (interchangeable units). Revision 1

    International Nuclear Information System (INIS)

    Waszink, R.P.; Hwang, J.Y.; Efferding, L.E.

    1974-06-01

    This is a preliminry thermal/hydraulic report reflecting work under Subtask 6.2 of Ref. 1.1. This report is an extension of the previous thermal/hydraulic design report. Parts of this report have been transmitted to GE. The detailed design basis, listed by source, is given. Additional details are discussed

  4. Investigation of coupling scheme for neutronic and thermal-hydraulic codes

    International Nuclear Information System (INIS)

    Wang Guoli; Yu Jianfeng; Pen Muzhang; Zhang Yuman.

    1988-01-01

    Recently, a number of coupled neutronics/thermal-hydraulics codes have been used in reaction design and safty analysis, which have been obtained by coupling previous neutronic and thermal-hydraulic codes. The different coupling schemes affect computer time and accuracy of calculation results. Numberical experiments of several different coupling schemes and some heuristic results are described

  5. Thermal-Hydraulic Experiments and Modelling for Advanced Nuclear Reactor Systems

    International Nuclear Information System (INIS)

    Song, C. H.; Chung, M. K.; Park, C. K. and others

    2005-04-01

    The objectives of the project are to study thermal hydraulic characteristics of reactor primary system for the verification of the reactor safety and to evaluate new safety concepts of new safety design features. To meet the research goal, several thermal hydraulic experiments were performed and related thermal hydraulic models were developed with the experimental data which were produced through the thermal hydraulic experiments. Followings are main research topics; - Multi-dimensional Phenomena in a Reactor Vessel Downcomer - Condensation Load and Thermal Mixing in the IRWST - Development of Thermal-Hydraulic Models for Two-Phase Flow - Development of Measurement Techniques for Two-Phase Flow - Supercritical Reactor T/H Characteristics Analysis From the above experimental and analytical studies, new safety design features of the advanced power reactors were verified and lots of the safety issues were also resolved

  6. Thermal-Hydraulic Experiments and Modelling for Advanced Nuclear Reactor Systems

    Energy Technology Data Exchange (ETDEWEB)

    Song, C. H.; Chung, M. K.; Park, C. K. and others

    2005-04-15

    The objectives of the project are to study thermal hydraulic characteristics of reactor primary system for the verification of the reactor safety and to evaluate new safety concepts of new safety design features. To meet the research goal, several thermal hydraulic experiments were performed and related thermal hydraulic models were developed with the experimental data which were produced through the thermal hydraulic experiments. Followings are main research topics; - Multi-dimensional Phenomena in a Reactor Vessel Downcomer - Condensation Load and Thermal Mixing in the IRWST - Development of Thermal-Hydraulic Models for Two-Phase Flow - Development of Measurement Techniques for Two-Phase Flow - Supercritical Reactor T/H Characteristics Analysis From the above experimental and analytical studies, new safety design features of the advanced power reactors were verified and lots of the safety issues were also resolved.

  7. Influence of physicians' life stances on attitudes to end-of-life decisions and actual end-of-life decision-making in six countries

    DEFF Research Database (Denmark)

    Cohen, J; van Delden, J; Mortier, F

    2008-01-01

    AIM: To examine how physicians' life stances affect their attitudes to end-of-life decisions and their actual end-of-life decision-making. METHODS: Practising physicians from various specialties involved in the care of dying patients in Belgium, Denmark, The Netherlands, Sweden, Switzerland......) and Protestants (up to 20.4% in The Netherlands) reported ever having made such a decision. DISCUSSION: The results suggest that religious teachings influence to some extent end-of-life decision-making, but are certainly not blankly accepted by physicians, especially when dealing with real patients...... large life-stance groups in each country. RESULTS: Only small differences in life stance were found in all countries in general attitudes and intended and actual behaviour with regard to various end-of-life decisions. However, with regard to the administration of drugs explicitly intended to hasten...

  8. End-of-Life Care Interventions: An Economic Analysis.

    Science.gov (United States)

    Pham, B; Krahn, M

    2014-01-01

    The annual cost of providing care for patients in their last year of life is estimated to account for approximately 9% of the Ontario health care budget. Access to integrated, comprehensive support and pain/symptom management appears to be inadequate and inequitable. To evaluate the cost-effectiveness of end-of-life (EoL) care interventions included in the EoL care mega-analysis. Multiple sources were used, including systematic reviews, linked health administration databases, survey data, planning documents, expert input, and additional literature searches. We conducted a literature review of cost-effectiveness studies to inform the primary economic analysis. We conducted the primary economic analysis and budget impact analysis for an Ontario cohort of decedents and their families and included interventions pertaining to team-based models of care, patient care planning discussions, educational interventions for patients and caregivers, and supportive interventions for informal caregivers. The time horizon was the last year of life. Costs were in 2013 Canadian dollars. Effectiveness measures included days at home, percentage dying at home, and quality-adjusted life-days. We developed a Markov model; model inputs were obtained from a cohort of Ontario decedents assembled from Institute for Clinical Evaluative Sciences databases and published literature. In-home palliative team care was cost-effective; it increased the chance of dying at home by 10%, increased the average number of days at home (6 days) and quality-adjusted life-days (0.5 days), and it reduced costs by approximately $4,400 per patient. Expanding in-home palliative team care to those currently not receiving such services (approximately 45,000 per year, at an annual cost of $76-108 million) is likely to improve quality of life, reduce the use of acute care resources, and save $191-$385 million in health care costs. Results for the other interventions were uncertain. The cost-effectiveness analysis was

  9. End-of-life care and mental illness: a model for community psychiatry and beyond.

    Science.gov (United States)

    Candilis, Philip J; Foti, Mary Ellen G; Holzer, Jacob C

    2004-02-01

    End-of-life care is often influenced by the stereotyping of patients by age, diagnosis, or cultural identity. Two common stereotypes arise from the presumed incompetence of many patients to contribute to end-of-life decisions, and the fear that the discussions themselves will be de-stabilizing. We present a model for end-of-life discussions that combines competence assessment with healthcare preferences in a psychiatric population that faces identical stereotypes. The model, which draws on clinical research in competence and suicide risk assessment, has important implications for all patients in the community who are marginalized or stereotyped during discussions of end-of-life treatment.

  10. Draft of the PHENIX Management Plan

    International Nuclear Information System (INIS)

    1994-01-01

    The PHENIX Management Plan provides the baselines and controls that the PHENIX and RHIC Projects will follow to meet the technical, cost, and schedule goals for the PHENIX detector at RHIC. This plan will be reviewed and updated as required, with revisions made by agreement among the signed participants

  11. The Phebus FP thermal-hydraulic analysis with Melcor

    International Nuclear Information System (INIS)

    Akgane, Kikuo; Kiso, Yoshihiro; Fukahori, Takanori; Yoshino, Mamoru

    1995-01-01

    The severe accident analysis code MELCOR, version 1.8.2, has been applied for thermal-hydraulic pre-test analysis of the first test of the Phebus FP program (test FPT-0) to study the best test parameters and the applicability of the code. The Phebus FP program is an in-pile test program which has been planned by the French Commissariate a L'Energie Atomique and the Commission of the European Union. The experiments are being conducted by an international collaboration to study the release and transport of fission products (FPs) under conditions assumed to be the most representative of those that would occur in a severe accident. The Phebus FP test apparatus simulates a test bundle of an in-pile section, the circuit including the steam generator U-tubes and the containment. The FPT-0 test was designed to simulate the heat-up and subsequent fuel bundle degradation after a loss of coolant severe accident, using fresh fuel. Two options for fuel degradation models in MELCOR have been applied to fuel degradation behavior. the first model assumes that fuel debris will be formed immediately after the fuel support fails by cladding relocation due to the candling process. The other is the uncollapsed bare fuel pellets option, in which the fuel pellets remain standing in a columnar shape until the fuel reaches its melting point, even if the cladding has been relocated by candling. The thermal-hydraulic behaviors in the circuit and containment of Phebus FP are discussed herein. Flow velocities in the Phebus FP circuit are high in order to produce turbulent flow in a small diameter test pipe. The MELCOR calculation has shown that the length of the hot leg and steam generator are adequate to attain steam temperatures or 700 degrees C and 150 degrees C in the respective outlets. The containment atmosphere temperature and humidity derived by once through integral system calculation show that objective test conditions would be satisfied in the Phebus FP experiment

  12. The Phebus FP thermal-hydraulic analysis with Melcor

    Energy Technology Data Exchange (ETDEWEB)

    Akgane, Kikuo; Kiso, Yoshihiro [Nuclear Power Engineering Corporation, Tokyo (Japan); Fukahori, Takanori [Hitachi Engineering Company, Ltd., Hitachi-shi Ibaraki-ken (Japan); Yoshino, Mamoru [Nuclear Engineering Ltd., Tosabori Nishi-ku (Japan)

    1995-09-01

    The severe accident analysis code MELCOR, version 1.8.2, has been applied for thermal-hydraulic pre-test analysis of the first test of the Phebus FP program (test FPT-0) to study the best test parameters and the applicability of the code. The Phebus FP program is an in-pile test program which has been planned by the French Commissariate a L`Energie Atomique and the Commission of the European Union. The experiments are being conducted by an international collaboration to study the release and transport of fission products (FPs) under conditions assumed to be the most representative of those that would occur in a severe accident. The Phebus FP test apparatus simulates a test bundle of an in-pile section, the circuit including the steam generator U-tubes and the containment. The FPT-0 test was designed to simulate the heat-up and subsequent fuel bundle degradation after a loss of coolant severe accident, using fresh fuel. Two options for fuel degradation models in MELCOR have been applied to fuel degradation behavior. the first model assumes that fuel debris will be formed immediately after the fuel support fails by cladding relocation due to the candling process. The other is the uncollapsed bare fuel pellets option, in which the fuel pellets remain standing in a columnar shape until the fuel reaches its melting point, even if the cladding has been relocated by candling. The thermal-hydraulic behaviors in the circuit and containment of Phebus FP are discussed herein. Flow velocities in the Phebus FP circuit are high in order to produce turbulent flow in a small diameter test pipe. The MELCOR calculation has shown that the length of the hot leg and steam generator are adequate to attain steam temperatures or 700{degrees}C and 150{degrees}C in the respective outlets. The containment atmosphere temperature and humidity derived by once through integral system calculation show that objective test conditions would be satisfied in the Phebus FP experiment.

  13. 'End of life could be on any ward really': A qualitative study of hospital volunteers' end-of-life care training needs and learning preferences.

    Science.gov (United States)

    Brighton, Lisa Jane; Koffman, Jonathan; Robinson, Vicky; Khan, Shaheen A; George, Rob; Burman, Rachel; Selman, Lucy Ellen

    2017-10-01

    Over half of all deaths in Europe occur in hospital, a location associated with many complaints. Initiatives to improve inpatient end-of-life care are therefore a priority. In England, over 78,000 volunteers provide a potentially cost-effective resource to hospitals. Many work with people who are dying and their families, yet little is known about their training in end-of-life care. To explore hospital volunteers' end-of-life care training needs and learning preferences, and the acceptability of training evaluation methods. Qualitative focus groups. Volunteers from a large teaching hospital were purposively sampled. Five focus groups were conducted with 25 hospital volunteers (aged 19-80 years). Four themes emerged as follows: preparation for the volunteering role, training needs, training preferences and evaluation preferences. Many described encounters with patients with life-threatening illness and their families. Perceived training needs in end-of-life care included communication skills, grief and bereavement, spiritual diversity, common symptoms, and self-care. Volunteers valued learning from peers and end-of-life care specialists using interactive teaching methods including real-case examples and role plays. A chance to 'refresh' training at a later date was suggested to enhance learning. Evaluation through self-reports or observations were acceptable, but ratings by patients, families and staff were thought to be pragmatically unsuitable owing to sporadic contact with each. Gaps in end-of-life care training for hospital volunteers indicate scope to maximise on this resource. This evidence will inform development of training and evaluations which could better enable volunteers to make positive, cost-effective contributions to end-of-life care in hospitals.

  14. End of life could be on any ward really’: A qualitative study of hospital volunteers’ end-of-life care training needs and learning preferences

    Science.gov (United States)

    Brighton, Lisa Jane; Koffman, Jonathan; Robinson, Vicky; Khan, Shaheen A; George, Rob; Burman, Rachel; Selman, Lucy Ellen

    2017-01-01

    Background: Over half of all deaths in Europe occur in hospital, a location associated with many complaints. Initiatives to improve inpatient end-of-life care are therefore a priority. In England, over 78,000 volunteers provide a potentially cost-effective resource to hospitals. Many work with people who are dying and their families, yet little is known about their training in end-of-life care. Aims: To explore hospital volunteers’ end-of-life care training needs and learning preferences, and the acceptability of training evaluation methods. Design: Qualitative focus groups. Setting/participants: Volunteers from a large teaching hospital were purposively sampled. Results: Five focus groups were conducted with 25 hospital volunteers (aged 19–80 years). Four themes emerged as follows: preparation for the volunteering role, training needs, training preferences and evaluation preferences. Many described encounters with patients with life-threatening illness and their families. Perceived training needs in end-of-life care included communication skills, grief and bereavement, spiritual diversity, common symptoms, and self-care. Volunteers valued learning from peers and end-of-life care specialists using interactive teaching methods including real-case examples and role plays. A chance to ‘refresh’ training at a later date was suggested to enhance learning. Evaluation through self-reports or observations were acceptable, but ratings by patients, families and staff were thought to be pragmatically unsuitable owing to sporadic contact with each. Conclusion: Gaps in end-of-life care training for hospital volunteers indicate scope to maximise on this resource. This evidence will inform development of training and evaluations which could better enable volunteers to make positive, cost-effective contributions to end-of-life care in hospitals. PMID:28056642

  15. On-Line Core Thermal-Hydraulic Model Improvement

    International Nuclear Information System (INIS)

    In, Wang Kee; Chun, Tae Hyun; Oh, Dong Seok; Shin, Chang Hwan; Hwang, Dae Hyun; Seo, Kyung Won

    2007-02-01

    The objective of this project is to implement a fast-running 4-channel based code CETOP-D in an advanced reactor core protection calculator system(RCOPS). The part required for the on-line calculation of DNBR were extracted from the source of the CETOP-D code based on analysis of the CETOP-D code. The CETOP-D code was revised to maintain the input and output variables which are the same as in CPC DNBR module. Since the DNBR module performs a complex calculation, it is divided into sub-modules per major calculation step. The functional design requirements for the DNBR module is documented and the values of the database(DB) constants were decided. This project also developed a Fortran module(BEST) of the RCOPS Fortran Simulator and a computer code RCOPS-SDNBR to independently calculate DNBR. A test was also conducted to verify the functional design and DB of thermal-hydraulic model which is necessary to calculate the DNBR on-line in RCOPS. The DNBR margin is expected to increase by 2%-3% once the CETOP-D code is used to calculate the RCOPS DNBR. It should be noted that the final DNBR margin improvement could be determined in the future based on overall uncertainty analysis of the RCOPS

  16. Engineered Barrier System Thermal-Hydraulic-Chemical Column Test Report

    International Nuclear Information System (INIS)

    W.E. Lowry

    2001-01-01

    The Engineered Barrier System (EBS) Thermal-Hydraulic-Chemical (THC) Column Tests provide data needed for model validation. The EBS Degradation, Flow, and Transport Process Modeling Report (PMR) will be based on supporting models for in-drift THC coupled processes, and the in-drift physical and chemical environment. These models describe the complex chemical interaction of EBS materials, including granular materials, with the thermal and hydrologic conditions that will be present in the repository emplacement drifts. Of particular interest are the coupled processes that result in mineral and salt dissolution/precipitation in the EBS environment. Test data are needed for thermal, hydrologic, and geochemical model validation and to support selection of introduced materials (CRWMS M and O 1999c). These column tests evaluated granular crushed tuff as potential invert ballast or backfill material, under accelerated thermal and hydrologic environments. The objectives of the THC column testing are to: (1) Characterize THC coupled processes that could affect performance of EBS components, particularly the magnitude of permeability reduction (increases or decreases), the nature of minerals produced, and chemical fractionation (i.e., concentrative separation of salts and minerals due to boiling-point elevation). (2) Generate data for validating THC predictive models that will support the EBS Degradation, Flow, and Transport PMR, Rev. 01

  17. Development of realistic thermal hydraulic system analysis code

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Won Jae; Chung, B. D; Kim, K. D. [and others

    2002-05-01

    The realistic safety analysis system is essential for nuclear safety research, advanced reactor development, safety analysis in nuclear industry and 'in-house' plant design capability development. In this project, we have developed a best-estimate multi-dimensional thermal-hydraulic system code, MARS, which is based on the integrated version of the RELAP5 and COBRA-TF codes. To improve the realistic analysis capability, we have improved the models for multi-dimensional two-phase flow phenomena and for advanced two-phase flow modeling. In addition, the GUI (Graphic User Interface) feature were developed to enhance the user's convenience. To develop the coupled analysis capability, the MARS code were linked with the three-dimensional reactor kinetics code (MASTER), the core thermal analysis code (COBRA-III/CP), and the best-estimate containment analysis code (CONTEMPT), resulting in MARS/MASTER/COBRA/CONTEMPT. Currently, the MARS code system has been distributed to 18 domestic organizations, including research, industrial, regulatory organizations and universities. The MARS has been being widely used for the safety research of existing PWRs, advanced PWR, CANDU and research reactor, the pre-test analysis of TH experiments, and others.

  18. Development of realistic thermal hydraulic system analysis code

    International Nuclear Information System (INIS)

    Lee, Won Jae; Chung, B. D; Kim, K. D.

    2002-05-01

    The realistic safety analysis system is essential for nuclear safety research, advanced reactor development, safety analysis in nuclear industry and 'in-house' plant design capability development. In this project, we have developed a best-estimate multi-dimensional thermal-hydraulic system code, MARS, which is based on the integrated version of the RELAP5 and COBRA-TF codes. To improve the realistic analysis capability, we have improved the models for multi-dimensional two-phase flow phenomena and for advanced two-phase flow modeling. In addition, the GUI (Graphic User Interface) feature were developed to enhance the user's convenience. To develop the coupled analysis capability, the MARS code were linked with the three-dimensional reactor kinetics code (MASTER), the core thermal analysis code (COBRA-III/CP), and the best-estimate containment analysis code (CONTEMPT), resulting in MARS/MASTER/COBRA/CONTEMPT. Currently, the MARS code system has been distributed to 18 domestic organizations, including research, industrial, regulatory organizations and universities. The MARS has been being widely used for the safety research of existing PWRs, advanced PWR, CANDU and research reactor, the pre-test analysis of TH experiments, and others

  19. Compatibility analysis of DUPIC fuel(4) - thermal hydraulic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Park, Jee Won; Chae, Kyung Myung; Choi, Hang Bok

    2000-07-01

    Thermal-hydraulic compatibility of the DUPIC fuel bundle in the CANDU reactor has been studied. The critical channel power, the critical power ratio, the channel exit quality and the channel flow are calculated for the DUPIC and the standard fuels by using the NUCIRC code. The physical models and associated parametric values for the NUCIRC analysis of the fuels are also presented. Based upon the slave channel analysis, the critical channel power and the critical power ratios have been found to be very similar for the two fuel types. The same dryout model is used in this study for the standard and the DUPIC fuel bundles. To assess the dryout characteristics of the DUPIC fuel bundle, the ASSERT-PV code has been used for the subchannel analysis. Based upon the results of the subchannel analysis, it is found that the dryout location and the power for the two fuel types are indeed very similar. This study shows that thermal performance of the DUPIC fuel is not significantly different from that of the standard fuel.

  20. VIPRE-01: A thermal-hydraulic code for reactor cores

    International Nuclear Information System (INIS)

    Cuta, J.M.; Koontz, A.S.; Stewart, C.W.; Montgomery, S.D.; Nomura, K.K.

    1989-08-01

    The VIPRE-01 thermal hydraulics code for PWR and BWR analysis has undergone significant modifications and error correction. This manual for the updated code, designated as VIPRE-01 Mod-02, describes improvements that eliminate problems of slow convergence with the drift flux model in transient simulation. To update the VIPRE-01 code and its documentation the drift flux model of two-phase flow was implemented and error corrections developed during VIPRE-01 application were included. The project team modified the existing VIPRE-01 equations into drift flux model equations by developing additional terms. They also developed and implemented corrections for the errors identified during the last four years. They then validated the modified code against standard test data using selected test cases. The project team prepared documentation revisions reflecting code improvements and corrections to replace the corresponding sections in the original VIPRE documents. The revised VIPRE code, designated VIPRE-01 Mod-02, incorporates improvements that eliminate many shortcomings of the previous version. During the validation, the code produced satisfactory output compared with test data. The revised documentation is in the form of binder pages to replace existing pages in three of the original manuals

  1. Thermal-hydraulic experiments for the PCHE type steam generator

    International Nuclear Information System (INIS)

    Shin, C. W.; No, H. C.

    2015-01-01

    Printed circuit heat exchanger (PCHE) manufactured by HEATRIC is a compact type of the mini-channel heat exchanger. The PCHE is manufactured by diffusion bonding of the chemically-etched plates, and has high heat transfer rate due to a large surface. Therefore, the size of heat exchanger can be reduced by 1/5 - 1/6 and PCHE can be operated under high pressure, high temperature and multi-phase flow. Under such merits, it is used as heat exchanger with various purposes of gas cycle and water cycle. Recently, it is newly suggested as an application of a steam generator. IRIS of MIT and FASES of KAIST conceptually adopted PCHE as a steam generator. When using boiling condition of micro-channel, flow instability is one of the critical issues. Instability may cause unstable mass flow rate, sudden temperature change and system control failure. However instability tests of micro channels using water are very limited because the previous studies were focused on a single tube or other fluid instead of water. In KAIST, we construct the test facility to study the thermal hydraulics and fluid dynamics of the heat exchanger, especially occurrence of instability. By inducing the pressure drop of inlet water, amplitude of oscillation declined by 90%. Finally, the throttling effect was experimentally confirmed that PCHE could be utilized as a steam generator

  2. Thermal hydraulic and neutronic interaction in the rotating bed reactor

    International Nuclear Information System (INIS)

    Lee, C.C.

    1986-01-01

    Power transient characteristics in a rotating fluidized bed reactor (RBR) are investigated theoretically. A propellant flow perturbation is assumed to occur in an initially equilibrium state of the core. Transfer functions representing quasi-one-dimensional mutual feedback between thermal hydraulics and neutronics are developed and analyzed in the frequency domain. Neutronic responses are determined by Fermi-age theory for slowing down of fast neutrons and diffusion theory for thermal neutron distribution. Neutron leakage through the exhaust nozzle is accounted for by applying diffuse view factors similar to those applied in radiative heat transfer. The bed expansion behavior is described by a kinematic wave equation derived from the continuity of the gas phase. The drift flux approach is used to determine the yield fractions in the equilibrium bed. Thermal responses of fuel are evaluated by dividing it into several volume-averaged zones to better account for the transient effects over single zone models. Sample calculations are undertaken for the various operation conditions and design parameters of the RBR based on 250 MW/sub t/, 1000 MW/sub t/, and 5000 MW/sub t/ power reactors. The results show that power transients are dependent on the parametric changes of optical thickness and view factors

  3. Thermal hydraulics model for Sandia's annular core research reactor

    International Nuclear Information System (INIS)

    Rao, Dasari V.; El-Genk, Mohamed S.; Rubio, Reuben A.; Bryson, James W.; Foushee, Fabian C.

    1988-01-01

    A thermal hydraulics model was developed for the Annular Core Research Reactor (ACRR) at Sandia National Laboratories. The coupled mass, momentum and energy equations for the core were solved simultaneously using an explicit forward marching numerical technique. The model predictions of the temperature rise across the central channel of the ACRR core were within ± 10 percent agreement with the in-core temperature measurements. The model was then used to estimate the coolant mass flow rate and the axial distribution of the cladding surface temperature in the central and average channels as functions of the operating power and the water inlet subcooling. Results indicated that subcooled boiling occurs at the cladding surface in the central channels of the ACRR at power levels in excess of 0.5 MW. However, the high heat transfer coefficient due to subcooled boiling causes the cladding temperature along most of the active fuel rod region to be quite uniform and to increase very little with the reactor power. (author)

  4. Thermal hydraulics analysis of the Advanced High Temperature Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Dean, E-mail: Dean_Wang@uml.edu [University of Massachusetts Lowell, One University Avenue, Lowell, MA 01854 (United States); Yoder, Graydon L.; Pointer, David W.; Holcomb, David E. [Oak Ridge National Laboratory, 1 Bethel Valley RD #6167, Oak Ridge, TN 37831 (United States)

    2015-12-01

    Highlights: • The TRACE AHTR model was developed and used to define and size the DRACS and the PHX. • A LOFF transient was simulated to evaluate the reactor performance during the transient. • Some recommendations for modifying FHR reactor system component designs are discussed. - Abstract: The Advanced High Temperature Reactor (AHTR) is a liquid salt-cooled nuclear reactor design concept, featuring low-pressure molten fluoride salt coolant, a carbon composite fuel form with embedded coated particle fuel, passively triggered negative reactivity insertion mechanisms, and fully passive decay heat rejection. This paper describes an AHTR system model developed using the Nuclear Regulatory Commission (NRC) thermal hydraulic transient code TRAC/RELAP Advanced Computational Engine (TRACE). The TRACE model includes all of the primary components: the core, downcomer, hot legs, cold legs, pumps, direct reactor auxiliary cooling system (DRACS), the primary heat exchangers (PHXs), etc. The TRACE model was used to help define and size systems such as the DRACS and the PHX. A loss of flow transient was also simulated to evaluate the performance of the reactor during an anticipated transient event. Some initial recommendations for modifying system component designs are also discussed. The TRACE model will be used as the basis for developing more detailed designs and ultimately will be used to perform transient safety analysis for the reactor.

  5. Nuclear reactor thermal hydraulics safety analysis and thoughts on FUKUSHIMA

    International Nuclear Information System (INIS)

    Ninokata, Hisashi

    2012-01-01

    The first part of this article is to show my thoughts on the accident at Fukushima Daiichi Nuclear Power Station. It is cited from a summary of my lecture talk in Indonesia, in the beginning of the last December, 2011. This talk was based on my previous lecture and seminar talks including those delivered at MIT, June 16, at the ANS Annual Meeting in Hollywood, Florida, June 28 at NURETH-13 in Toronto, September 27, and others. The content is based on the open and latest information available to date in Japan. It may contain some erroneous or uncertain information. I tried to minimize it to my best capability. Also I tried to eliminate any critical issues or opinions that may jeopardize some people who were involved in. The latter half of this article will be excerpts of my recent R and D activities related to the safety-by-design for sodium cooled fast reactors and light water reactors, thermal hydraulics analysis focusing on the simulation-based technology, in particular subchannel analysis and computational fluid dynamics. (J.P.N.)

  6. Thermal hydraulic analysis of the JMTR improved LEU-core

    Energy Technology Data Exchange (ETDEWEB)

    Tabata, Toshio; Nagao, Yoshiharu; Komukai, Bunsaku; Naka, Michihiro; Fujiki, Kazuo [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment; Takeda, Takashi [Radioactive Waste Management and Nuclear Facility Decommissioning Technology Center, Tokai, Ibaraki (Japan)

    2003-01-01

    After the investigation of the new core arrangement for the JMTR reactor in order to enhance the fuel burn-up and consequently extend the operation period, the ''improved LEU core'' that utilized 2 additional fuel elements instead of formerly installed reflector elements, was adopted. This report describes the results of the thermal-hydraulic analysis of the improved LEU core as a part of safety analysis for the licensing. The analysis covers steady state, abnormal operational transients and accidents, which were described in the annexes of the licensing documents as design bases events. Calculation conditions for the computer codes were conservatively determined based on the neutronic analysis results and others. The results of the analysis, that revealed the safety criteria were satisfied on the fuel temperature, DNBR and primary coolant temperature, were used in the licensing. The operation license of the JMTR with the improved LEU core was granted in March 2001, and the reactor operation with new core started in November 2001 as 142nd operation cycle. (author)

  7. Parallelization methods study of thermal-hydraulics codes

    International Nuclear Information System (INIS)

    Gaudart, Catherine

    2000-01-01

    The variety of parallelization methods and machines leads to a wide selection for programmers. In this study we suggest, in an industrial context, some solutions from the experience acquired through different parallelization methods. The study is about several scientific codes which simulate a large variety of thermal-hydraulics phenomena. A bibliography on parallelization methods and a first analysis of the codes showed the difficulty of our process on the whole applications to study. Therefore, it would be necessary to identify and extract a representative part of these applications and parallelization methods. The linear solver part of the codes forced itself. On this particular part several parallelization methods had been used. From these developments one could estimate the necessary work for a non initiate programmer to parallelize his application, and the impact of the development constraints. The different methods of parallelization tested are the numerical library PETSc, the parallelizer PAF, the language HPF, the formalism PEI and the communications library MPI and PYM. In order to test several methods on different applications and to follow the constraint of minimization of the modifications in codes, a tool called SPS (Server of Parallel Solvers) had be developed. We propose to describe the different constraints about the optimization of codes in an industrial context, to present the solutions given by the tool SPS, to show the development of the linear solver part with the tested parallelization methods and lastly to compare the results against the imposed criteria. (author) [fr

  8. CFD thermal-hydraulic analysis of a CANDU fuel channel

    International Nuclear Information System (INIS)

    Catana, A.; Prisecaru, I.; Dupleac, D.; Danila, N.

    2009-01-01

    This paper presents the numerical investigation of a CANDU fuel channel using CFD (Computational fluid dynamics) methodology approach. Limited computer power available at Bucharest University POLITEHNICA forced the authors to analyse only segments of fuel channel namely the significant ones: fuel bundle junctions with adjacent segments, fuel bundle spacer planes with adjacent segments, regular segments of fuel bundles. The computer code used is FLUENT. Fuel bundles contained in pressure tubes forms a complex flow domain. The flow is characterized by high turbulence and in some parts of fuel channel also by multi-phase flow. The flow in the fuel channel has been simulated by solving the equations for conservation of mass and momentum. For turbulence modelling the standard k-e model is employed although other turbulence models can be used as well. In this paper we do not consider heat generation and heat transfer capabilities of CFD methods. Since we consider only some relatively short segments of a CANDU fuel channel we can assume, for this starting stage, that heat transfer is not very important for these short segments of fuel channel. The boundary conditions for CFD analysis are provided by system and sub-channel analysis. In this paper the discussion is focused on some flow parameters behaviour at the bundle junction, spacer's plane configuration, etc. In this paper we present results for Standard CANDU 6 Fuel Bundles as a basis for CFD thermal-hydraulic analysis of INR proposed SEU43 and other new nuclear fuels. (authors)

  9. Thermal Hydraulic Analysis of RPV Support Cooling System for HTGR

    International Nuclear Information System (INIS)

    Min Qi; Wu Xinxin; Li Xiaowei; Zhang Li; He Shuyan

    2014-01-01

    Passive safety is now of great interest for future generation reactors because of its reduction of human interaction and avoidance of failures of active components. reactor pressure vessel (RPV) support cooling system (SCS) for high temperature gas-cooled reactor (HTGR) is a passive safety system and is used to cool the concrete seats for the four RPV supports at its bottom. The SCS should have enough cooling capacity to ensure the temperature of the concrete seats for the supports not exceeding the limit temperature. The SCS system is composed of a natural circulation water loop and an air cooling tower. In the water loop, there is a heat exchanger embedded in the concrete seat, heat is transferred by thermal conduction and convection to the cooling water. Then the water is cooled by the air cooler mounted in the air cooling tower. The driving forces for water and air are offered by the density differences caused by the temperature differences. In this paper, the thermal hydraulic analysis for this system was presented. Methods for decoupling the natural circulation and heat transfer between the water loop and air flow were introduced. The operating parameters for different working conditions and environment temperatures were calculated. (author)

  10. One-dimensional two-phase thermal hydraulics (ENSTA course)

    International Nuclear Information System (INIS)

    Olive, J.

    1995-11-01

    This course is part of the ENSTA 3rd year thermal hydraulics program (nuclear power option). Its purpose is to provide the theoretical basis and main physical notions pertaining to two-phase flow, mainly focussed on water-steam flows. The introduction describes the physical specificities of these flows, emphasizing their complexity. The mathematical bases are then presented (partial derivative equations), leading to a one-dimensional type, simplified description. Balances drawn up for a pipe length volume are used to introduce the mass conservation. motion and energy equations for each phase. Various postulates used to simplify two-phase models are presented, culminating in homogeneous model definitions and equations, several common examples of which are given. The model is then applied to the calculation of pressure drops in two-phase flows. This involves presenting the models most frequently used to represent pressure drops by friction or due to pipe irregularities, without giving details (numerical values of parameters). This chapter terminates with a brief description of static and dynamic instabilities in two-phase flows. Finally, heat transfer conditions frequently encountered in liquid-steam flows are described, still in the context of a 1D model. This chapter notably includes reference to under-saturated boiling conditions and the various forms of DNB. The empirical heat transfer laws are not discussed in detail. Additional material is appended, some of which is in the form of corrected exercises. (author). 6 appends

  11. Development of fuel performance and thermal hydraulic technology

    International Nuclear Information System (INIS)

    Jung, Youn Ho; Song, K. N.; Kim, H. K. and others

    2000-03-01

    Space grid in LWR fuel assembly is a key structural component to support fuel rods and to enhance heat transfer from fuel rod to the coolant. Therefore, the original spacer grid has been developed. In addition, new phenomena in fuel behavior occurs at the high burnup, so that models to analyze those new phenomena were developed. Results of this project can be summarized as follows. - Seven different spacer grid candidates have been invented and submitted for domestic and US patents. Spacer grid test specimen(3x3 array and 5x5 array) were fabricated for each candidate and the mechanical tests were performed. - Basic technologies in the mechanical and thermal hydraulic behavior in the spacer grid development are studied and relevant test facilities were established - Fuel performance analysis models and programs were developed for the high burnup pellet and cladding, and fuel performance data base were compiled - Procedures of fuel characterization and in-/out of-pile tests were prepared - Conceptual design of fuel rod for integral PWR was carried out. (author)

  12. Local thermal-hydraulic behaviour in tight 7-rod bundles

    International Nuclear Information System (INIS)

    Cheng, X.; Yu, Y.Q.

    2009-01-01

    Advanced water-cooled reactor concepts with tight lattices have been proposed worldwide to improve the fuel utilization and the economic competitiveness. In the present work, experimental investigations were performed on thermal-hydraulic behaviour in tight hexagonal 7-rod bundles under both single-phase and two-phase conditions. Freon-12 was used as working fluid due to its convenient operating parameters. Tests were carried out under both single-phase and two-phase flow conditions. Rod surface temperatures are measured at a fixed axial elevation and in various circumferential positions. Test data with different radial power distributions are analyzed. Measured surface temperatures of unheated rods are used for the assessment of and comparison with numerical codes. In addition, numerical simulation using sub-channel analysis code MATRA and the computational fluid dynamics (CFD) code ANSYS-10 is carried out to understand the experimental data and to assess the validity of these codes in the prediction of flow and heat transfer behaviour in tight rod bundle geometries. Numerical results are compared with experimental data. A good agreement between the measured temperatures on the unheated rod surface and the CFD calculation is obtained. Both sub-channel analysis and CFD calculation indicates that the turbulent mixing in the tight rod bundle is significantly stronger than that computed with a well established correlation.

  13. On-Line Core Thermal-Hydraulic Model Improvement

    Energy Technology Data Exchange (ETDEWEB)

    In, Wang Kee; Chun, Tae Hyun; Oh, Dong Seok; Shin, Chang Hwan; Hwang, Dae Hyun; Seo, Kyung Won

    2007-02-15

    The objective of this project is to implement a fast-running 4-channel based code CETOP-D in an advanced reactor core protection calculator system(RCOPS). The part required for the on-line calculation of DNBR were extracted from the source of the CETOP-D code based on analysis of the CETOP-D code. The CETOP-D code was revised to maintain the input and output variables which are the same as in CPC DNBR module. Since the DNBR module performs a complex calculation, it is divided into sub-modules per major calculation step. The functional design requirements for the DNBR module is documented and the values of the database(DB) constants were decided. This project also developed a Fortran module(BEST) of the RCOPS Fortran Simulator and a computer code RCOPS-SDNBR to independently calculate DNBR. A test was also conducted to verify the functional design and DB of thermal-hydraulic model which is necessary to calculate the DNBR on-line in RCOPS. The DNBR margin is expected to increase by 2%-3% once the CETOP-D code is used to calculate the RCOPS DNBR. It should be noted that the final DNBR margin improvement could be determined in the future based on overall uncertainty analysis of the RCOPS.

  14. Thermal Hydraulic Analysis Of Thorium-Based Annular Fuel Assemblies

    Energy Technology Data Exchange (ETDEWEB)

    Han, Kyu Hyun [Korea Institute of Nuclear Safety, 19, Guseong-dong, Yuseong-gu, Daejeon, 305-338 (Korea, Republic of)

    2008-07-01

    Thermal hydraulic characteristics of thorium-based fuel assemblies loaded with annular seed pins have been analyzed using AMAP combined with MATRA, and compared with those of the existing thorium-based assemblies. MATRA and AMAP showed good agreements for the pressure drops at the internal sub-channels. The pressure drop generally increased in the cases of the assemblies loaded with annular seed pins due to the larger wetted perimeter, but an exception existed. In the inner sub-channels of the seed pins, mass fluxes were high due to the grid form losses in the outer sub-channels. About 43% of the heat generated from the seed pin flowed into the inner sub-channel and the rest into the outer sub-channel, which implies the inner to outer wall heat flux ratio was approximately 1.2. The maximum temperatures of the annular seed pins were slightly above 500 deg. C. The MDNBRs of the assemblies loaded with annular seed pins were higher than those of the existing assemblies. Due to the fact that inter-channel mixing cannot occur in the inner sub-channels, temperatures and enthalpies were higher in the inner sub-channels. (author)

  15. Thermal-hydraulic experiments and analyses on cold moderator

    International Nuclear Information System (INIS)

    Aso, Tomokazu; Kaminaga, Masanori; Terada, Atsushi; Hino, Ryutaro

    2001-01-01

    A cold moderator using supercritical hydrogen is one of the key components in a MW-scale spallation target system, which directly affects the neutronic performance both in intensity and resolution. Since a hydrogen temperature rise in the moderator vessel affects the neutronic performance, it is necessary to suppress the local temperature rise within 3 K. In order to develop the conceptual design of the moderator structure in progress, the flow patterns were measured using a PIV (Particle Image Velocimeter) system under water flow conditions using a flat model that simulated a moderator vessel. From these results, the flow patterns (such as recirculation flows, stagnant flows etc.) were clarified. The hydraulic analytical results obtained using the STAR-CD code agreed well with experimental results. Thermal-hydraulic analyses in the moderator vessel were carried out using the STAR-CD code. Based on these results, we clarified the possibility of suppressing the local temperature rise to within 3 K under 2 MW operating conditions. In order to achieve the cost decreasing of the hydrogen loop, it is necessary to operate it reducing the hydrogen flow rate and the whole hydrogen mass. Then improved moderator concept using blowholes and a twisted tape was proposed, and we have tried to examine the effect of the blowing flow from the inlet pipe. From the experimental and analytical results, the blowing flow could be feasible for the suppression of the stagnant region. (author)

  16. End-of-life decisions for people with intellectual disabilities, an interview study with patient representatives

    NARCIS (Netherlands)

    Wagemans, A.M.; Schrojenstein Lantman-de Valk, H.M. van; Proot, I.M.; Metsemakers, J.; Tuffrey-Wijne, I.; Curfs, L.M.G.

    2013-01-01

    Background: Not much is known about the process of end-of-life decision-making for people with intellectual disabilities. Aim: To clarify the process of end-of-life decision-making for people with intellectual disabilities from the perspective of patient representatives. Design: A qualitative study

  17. Interviews on end-of-life care with older people: reflections on six european studies

    NARCIS (Netherlands)

    Pleschberger, S.; Seymour, J.E.; Payne, S.; Deschepper, R.; Onwuteaka-Philipsen, B.D.; Rurup, M.L.

    2011-01-01

    Qualitative research provides important insights into the experiences and perspectives of older people on end-of-life issues, but such research is methodologically and ethically complex. We offer a set of reflections from six end-of-life care studies conducted with older people in four European

  18. Selection bias in family reports on end of life with dementia in nursing homes

    NARCIS (Netherlands)

    van der Steen, J.T.; Deliens, L.; Ribbe, M.W.; Onwuteaka-Philipsen, B.D.

    2012-01-01

    Background: Selective participation in retrospective studies of families recruited after the patient's death may threaten generalizability of reports on end-of-life experiences. Objectives: To assess possible selection bias in retrospective study of dementia at the end of life using family reports.

  19. End-of-Life Care Education for Psychiatric Residents: Attitudes, Preparedness, and Conceptualizations of Dignity

    Science.gov (United States)

    Tait, Glendon R.; Hodges, Brian D.

    2009-01-01

    Objective: The authors examined psychiatric residents' attitudes, perceived preparedness, experiences, and needs in end-of-life care education. They also examined how residents conceptualized good end-of-life care and dignity. Methods: The authors conducted an electronic survey of 116 psychiatric residents at the University of Toronto. The survey…

  20. Good end-of-life care according to patients and their GPs

    NARCIS (Netherlands)

    Borgsteede, Sander D.; Graafland-Riedstra, Corrie; Deliens, Luc; Francke, Anneke L.; van Eijk, Jacques ThM; Willems, Dick L.

    2006-01-01

    BACKGROUND: Most patients prefer to die at home, where a GP provides end-of-life care. A few previous studies have been directed at the GPs' values on good end-of-life care, yet no study combined values of patients and their own GP. AIM: To explore the aspects valued by both patients and GPs in

  1. The broad spectrum of unbearable suffering in end of life cancer studied in dutch primary care

    NARCIS (Netherlands)

    Ruijs, C.D.M.; Kerkhof, A.J.F.M.; van der Wal, G.; Onwuteaka-Philipsen, B.D.

    2012-01-01

    Background: Unbearable suffering most frequently is reported in end-of-life cancer patients in primary care. However, research seldom addresses unbearable suffering. The aim of this study was to comprehensively investigate the various aspects of unbearable suffering in end-of-life cancer patients

  2. Do Older Korean Immigrants Engage in End-of-Life Communication?

    Science.gov (United States)

    Ko, Eunjeong; Roh, Soonhee; Higgins, Doreen

    2013-01-01

    End-of-life communication is an important process as it allows individuals' treatment preferences to be known, yet not every culture is receptive to such discussions. Planning for end-of-life care is not readily supported in Asian culture, and little is known about individuals' communication with family and health care professionals among older…

  3. End-of-life decisions: an important theme in the care for people with intellectual disabilities.

    NARCIS (Netherlands)

    Wagemans, A.; Schrojenstein Lantman, H.M.J. van; Tuffrey-Wijne, I.; Widdershoven, G.; Curfs, L.M.G.

    2010-01-01

    BACKGROUND: While end-of-life decisions in the general population have received attention in several countries, not much is known about this in people with intellectual disabilities (IDs). Therefore, the prevalence and nature of end-of-life decisions were investigated in a Dutch centre providing

  4. Looking at the end-of-life directive and challenges in recycling

    DEFF Research Database (Denmark)

    Smink, Carla

    2004-01-01

    The article deals with end-of-life vechile regulations. Focus is on the European end-of-life vechile directive (2000/53/EC) and how Denmark and the Netherlands have dealt with the regulations in the past 30 years....

  5. Nurse involvement in end-of-life decision making: the ETHICUS Study

    DEFF Research Database (Denmark)

    Benbenishty, Julie; Ganz, Freda DeKeyser; Lippert, Anne

    2006-01-01

    The purpose was to investigate physicians' perceptions of the role of European intensive care nurses in end-of-life decision making.......The purpose was to investigate physicians' perceptions of the role of European intensive care nurses in end-of-life decision making....

  6. Good end-of-life care according to patients and their GPs.

    NARCIS (Netherlands)

    Borgsteede, S.D.; Graafland-Riedstra, C.; Deliens, L.; Francke, A.L.; Eijk, J.T.M. van; Willems, D.L.

    2006-01-01

    Background: Most patients prefer to die at home, where a GP provides end-of-life care. A few previous studies have been directed at the GPs' values on good end-of-life care, yet no study combined values of patients and their own GP. Aim: To explore the aspects valued by both patients and GPs in

  7. Aging Prisoners' Treatment Selection: Does Prospect Theory Enhance Understanding of End-of-Life Medical Decisions?

    Science.gov (United States)

    Phillips, Laura L.; Allen, Rebecca S.; Harris, Grant M.; Presnell, Andrew H.; DeCoster, Jamie; Cavanaugh, Ronald

    2011-01-01

    Purpose: With the rapid growth in the older inmate population and the economic impact of end-of-life treatments within the cash-strapped prison system, consideration should be given to inmate treatment preferences. We examined end-of-life treatment preferences and days of desired life for several health scenarios among male inmates incarcerated…

  8. BWR 9 X 9 Fuel Assembly Thermal-Hydraulic Tests (2): Hydraulic Vibration Test

    International Nuclear Information System (INIS)

    Yoshiaki Tsukuda; Katsuichiro Kamimura; Toshiitsu Hattori; Akira Tanabe; Noboru Saito; Masahiko Warashina; Yuji Nishino

    2002-01-01

    Nuclear Power Engineering Corporation (NUPEC) conducted thermal-hydraulic projects for verification of thermal-hydraulic design reliability for BWR high-burnup 8 x 8 and 9 x 9 fuel assemblies, entrusted by the Ministry of Economy, Trade and Industry (METI). As a part of the NUPEC thermal-hydraulic projects, hydraulic vibration tests using full-scale test assemblies simulating 9 x 9 fuel assemblies were carried out to evaluate BWR fuel integrity. The test data were applied to development of a new correlation for the estimation of fuel rod vibration amplitude. (authors)

  9. Pain and symptom management in palliative care and at end of life.

    Science.gov (United States)

    Wilkie, Diana J; Ezenwa, Miriam O

    2012-01-01

    The purpose of this review is to provide a literature update of the research published since 2004 on pain and symptom management in palliative care and at end of life. Findings suggest that pain and symptoms are inadequately assessed and managed, even at the end of life. Although not pervasive, there is evidence of racial/ethnic disparities in symptom management in palliative care and at end of life. There is a need for a broader conceptualization and measurement of pain and symptom management as multidimensional experiences. There is insufficient evidence about mechanisms underlying pain at end of life. Although there are advances in the knowledge of pain as a multidimensional experience and the many symptoms that occur sometimes with pain, gaps remain. One approach to addressing the gaps will involve assessment and management of pain and symptoms as multidimensional experiences in people receiving palliative care and at end of life. Copyright © 2012 Elsevier Inc. All rights reserved.

  10. Involving healthcare professionals and family carers in setting research priorities for end-of-life care.

    Science.gov (United States)

    Diffin, Janet; Spence, Michael; Spencer, Rebecca; Mellor, Peter; Grande, Gunn

    2017-02-02

    It is important to ensure regional variances are considered when setting future end-of-life research priorities, given the differing demographics and service provision. This project sought to identify end-of-life research priorities within Greater Manchester (United Kingdom). Following an initial scoping exercise, six topics within the 10 national priorities outlined by The Palliative and end-of-life care Priority Setting Partnership were selected for exploration. A workshop involving 32 healthcare professionals and a consultation process with 26 family carers was conducted. Healthcare professionals and carers selected and discussed the topics important to them. The topics selected most frequently by both healthcare professionals and carers were 'Access to 24 hour care', 'Planning end-of-life care in advance' and 'Staff and carer education'. Healthcare professionals also developed research questions for their topics of choice which were refined to incorporate carers' views. These questions are an important starting point for future end-of-life research within Greater Manchester.

  11. Effects of a Simulation Exercise on Nursing Students' End-of-Life Care Attitudes.

    Science.gov (United States)

    Dame, Linda; Hoebeke, Roberta

    2016-12-01

    Students consider end-of-life care content in their nursing curricula to be inadequate and deficient in promoting the development of the necessary attitudes to care for dying patients. Research identifies simulation as an effective teaching strategy to examine nursing students' attitudes toward end-of-life care. An end-of-life care simulation was developed, implemented, and evaluated. Attitudes toward caring for dying patients were measured pre- and postsimulation on a convenience sample of 57 sophomore nursing students using the Frommelt Attitudes Toward Care of the Dying Scale-Form B. Repeated measures of ANOVA on outcome variables evaluated student attitudes toward end-of-life care. Participation in an end-of-life care simulation resulted in more positive student attitudes toward caring for dying patients (p life care in nursing curricula and improve student attitudes toward caring for dying patients. [J Nurs Educ. 2016;55(12):701-705.]. Copyright 2016, SLACK Incorporated.

  12. NEPTUNE: A new software platform for advanced nuclear thermal hydraulics

    International Nuclear Information System (INIS)

    Guelfi, A.; Boucker, M.; Herard, J.M.; Peturaud, P.; Bestion, D.; Boudier, P.; Hervieu, E.; Fillion, P.; Grandotto, M.

    2007-01-01

    The NEPTUNE project constitutes the thermal-hydraulic part of the long-term Electricite de France and Commissariat a l'Energie Atomique joint research and development program for the next generation of nuclear reactor simulation tools. This program is also financially supported by the Institut de Radioprotection et Surete Nucleaire and AREVA NP. The project aims at developing a new software platform for advanced two-phase flow thermal hydraulics covering the whole range of modeling scales and allowing easy multi-scale and multidisciplinary calculations. NEPTUNE is a fully integrated project that covers the following fields: software development, research in physical modeling and numerical methods, development of advanced instrumentation techniques, and performance of new experimental programs. The analysis of the industrial needs points out that three main simulation scales are involved. The system scale is dedicated to the overall description of the reactor. The component or subchannel scale allows three-dimensional computations of the main components of the reactors: cores, steam generators, condensers, and heat exchangers. The current generation of system and component codes has reached a very high level of maturity for industrial applications. The third scale, computational fluid dynamics (CFD) in open medium, allows one to go beyond the limits of the component scale for a finer description of the flows. This scale opens promising perspectives for industrial simulations, and the development and validation of the NEPTUNE CFD module have been a priority since the beginning of the project. It is based on advanced physical models (two-fluid or multi field model combined with interfacial area transport and two-phase turbulence) and modern numerical methods (fully unstructured finite volume solvers). For the system and component scales, prototype developments have also started, including new physical models and numerical methods. In addition to scale

  13. Isotope Production Facility Conceptual Thermal-Hydraulic Design Review and Scoping Calculations

    International Nuclear Information System (INIS)

    Pasamehmetoglu, K.O.; Shelton, J.D.

    1998-01-01

    The thermal-hydraulic design of the target for the Isotope Production Facility (IPF) is reviewed. In support of the technical review, scoping calculations are performed. The results of the review and scoping calculations are presented in this report

  14. Progress of the DUPIC fuel compatibility analysis (II) - thermal-hydraulics

    Energy Technology Data Exchange (ETDEWEB)

    Park, Joo Hwan; Choi, Hang Bok

    2005-03-01

    Thermal-hydraulic compatibility of the DUPIC fuel bundle with a 713 MWe Canada deuterium uranium (CANDU-6) reactor was studied by using both the single channel and sub-channel analysis methods. The single channel analysis provides the fuel channel flow rate, pressure drop, critical channel power, and the channel exit quality, which are assessed against the thermal-hydraulic design requirements of the CANDU-6 reactor. The single channel analysis by the NUCIRC code showed that the thermal-hydraulic performance of the DUPIC fuel is not different from that of the standard CANDU fuel. Regarding the local flow characteristics, the sub-channel analysis also showed that the uncertainty of the critical channel power calculation for the DUPIC fuel channel is very small. As a result, both the single and sub-channel analyses showed that the key thermal-hydraulic parameters of the DUPIC fuel channel do not deteriorate compared to the standard CANDU fuel channel.

  15. Development of thermal hydraulic models for the reliable regulatory auditing code

    Energy Technology Data Exchange (ETDEWEB)

    Chung, B. D.; Song, C. H.; Lee, Y. J.; Kwon, T. S. [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    2003-04-15

    The objective of this project is to develop thermal hydraulic models for use in improving the reliability of the regulatory auditing codes. The current year fall under the first step of the 3 year project, and the main researches were focused on identifying the candidate thermal hydraulic models for improvement and to develop prototypical model development. During the current year, the verification calculations submitted for the APR 1400 design certification have been reviewed, the experimental data from the MIDAS DVI experiment facility in KAERI have been analyzed and evaluated, candidate thermal hydraulic models for improvement have been identified, prototypical models for the improved thermal hydraulic models have been developed, items for experiment in connection with the model development have been identified, and preliminary design of the experiment has been carried out.

  16. Development of thermal hydraulic models for the reliable regulatory auditing code

    International Nuclear Information System (INIS)

    Chung, B. D.; Song, C. H.; Lee, Y. J.; Kwon, T. S.

    2003-04-01

    The objective of this project is to develop thermal hydraulic models for use in improving the reliability of the regulatory auditing codes. The current year fall under the first step of the 3 year project, and the main researches were focused on identifying the candidate thermal hydraulic models for improvement and to develop prototypical model development. During the current year, the verification calculations submitted for the APR 1400 design certification have been reviewed, the experimental data from the MIDAS DVI experiment facility in KAERI have been analyzed and evaluated, candidate thermal hydraulic models for improvement have been identified, prototypical models for the improved thermal hydraulic models have been developed, items for experiment in connection with the model development have been identified, and preliminary design of the experiment has been carried out

  17. Proceedings of the 10. Meeting on Reactor Physics and Thermal Hydraulics

    International Nuclear Information System (INIS)

    Santos Bastos, W. dos

    1995-01-01

    These proceedings presents all the Meeting papers emphasizing specific aspects on reactor physics method, criticality, fuel management, nuclear data, safety analysis, simulation and shielding, neutronics, thermal hydraulics, reactor operation and computational methods

  18. Computational features of the MELT-III neutronics, thermal-hydraulics computer code system

    International Nuclear Information System (INIS)

    Wilburn, N.P.; Waltar, A.E.

    1976-01-01

    A multichannel, thermal-hydraulics, neutronic accident analysis program for simulating fast reactor behavior from a hypothetical accident inception to the start of core disassembly or to reactor shutdown is described

  19. Study of thermal-hydraulic analyses with CIP method

    International Nuclear Information System (INIS)

    Doi, Yoshihiro

    1996-09-01

    New type of numerical scheme CIP has been proposed for solving hyperbolic type equations and the CIP is focused on as a less numerical diffusive scheme. C-CUP method with the CIP scheme is adopted to numerical simulations that treat compressible and incompressible fluids, phase change phenomena and Mixture fluids. To evaluate applicabilities of the CIP scheme and C-CUP method for thermal hydraulic analyses related to Fast Breeder Reactors (FBRs), the scheme and the method were reviewed. Feature of the CIP scheme and procedure of the C-CUP method were presented. The CIP scheme is used to solve linear hyperbolic type equations for advection term in basic equations of fluids. Key issues of the scheme is that profile between grid points is described to solve the equation by cubic polynomial and spatial derivatives of the polynomial. The scheme can capture steep change of solution and suppress numerical error. In the C-CUP method, the basic equations of fluids are divided into advection terms and the other terms. The advection terms is solved with CIP scheme and the other terms is solved with difference method. The C-CUP method is robust for numerical instability, but mass of fluid will be in unfair preservation with nonconservative equations for fluids. Numerical analyses with the CIP scheme and the C-CUP method has been performed for phase change, mixture and moving object. These analyses are depend on characteristics of that the scheme and the method are robust for steep change of density and useful for interface tracking. (author)

  20. Validation of thermal hydraulic codes for fusion reactors safety

    International Nuclear Information System (INIS)

    Sardain, P.; Gulden, W.; Massaut, V.; Takase, K.; Merill, B.; Caruso, G.

    2006-01-01

    A significant effort has been done worldwide on the validation of thermal hydraulic codes, which can be used for the safety assessment of fusion reactors. This work is an item of an implementing agreement under the umbrella of the International Energy Agency. The European part is supported by EFDA. Several programmes related to transient analysis in water-cooled fusion reactors were run in order to assess the capabilities of the codes to treat the main physical phenomena governing the accidental sequences related to water/steam discharge into the vacuum vessel or the cryostat. The typical phenomena are namely the pressurization of a volume at low initial pressure, the critical flow, the flashing, the relief into an expansion volume, the condensation of vapor in a pressure suppression system, the formation of ice on a cryogenic structure, the heat transfer between walls and fluid in various thermodynamic conditions. · A benchmark exercise has been done involving different types of codes, from homogeneous equilibrium to six equations non-equilibrium models. Several cases were defined, each one focusing on a particular phenomenon. · The ICE (Ingress of Coolant Event) facility has been operated in Japan. It has simulated an in-vessel LOCA and the discharge of steam into a pressure suppression system. · The EVITA (European Vacuum Impingement Test Apparatus) facility has been operated in France. It has simulated ingress of coolant into the cryostat, i.e. into a volume at low initial pressure containing surfaces at cryogenic temperature. This paper gives the main lessons gained from these programs, in particular the possibilities for the improvement of the computer codes, extending their capabilities. For example, the water properties have been extended below the triple point. Ice formation models have been implemented. Work has also been done on condensation models. The remaining needs for R-and-D are also highlighted. (author)

  1. VIPRE-01. a thermal-hydraulic analysis code for reactor cores. Volume 1. Mathematical modeling

    International Nuclear Information System (INIS)

    Stewart, C.W.; Cuta, J.M.; Koontz, A.S.; Kelly, J.M.; Basehore, K.L.; George, T.L.; Rowe, D.S.

    1983-04-01

    VIPRE (Versatile Internals and Component Program for Reactors; EPRI) has been developed for nuclear power utility thermal-hydraulic analysis applications. It is designed to help evaluate nuclear reactor core safety limits including minimum departure from nucleate boiling ratio (MDNBR), critical power ratio (CPR), fuel and clad temperatures, and coolant state in normal operation and assumed accident conditions. This volume (Volume 1: Mathematical Modeling) explains the major thermal hydraulic models and supporting correlations in detail

  2. Current and anticipated uses of thermal-hydraulic codes in NFI

    Energy Technology Data Exchange (ETDEWEB)

    Tsuda, K. [Nuclear Fuel Industries, Ltd., Tokyo (Japan); Takayasu, M. [Nuclear Fuel Industries, Ltd., Sennann-gun (Japan)

    1997-07-01

    This paper presents the thermal-hydraulic codes currently used in NFI for the LWR fuel development and licensing application including transient and design basis accident analyses of LWR plants. The current status of the codes are described in the context of code capability, modeling feature, and experience of code application related to the fuel development and licensing. Finally, the anticipated use of the future thermal-hydraulic code in NFI is briefly given.

  3. Thermal-hydraulic code selection for modular high temperature gas-cooled reactors

    Energy Technology Data Exchange (ETDEWEB)

    Komen, E M.J.; Bogaard, J.P.A. van den

    1995-06-01

    In order to study the transient thermal-hydraulic system behaviour of modular high temperature gas-cooled reactors, the thermal-hydraulic computer codes RELAP5, MELCOR, THATCH, MORECA, and VSOP are considered at the Netherlands Energy Research Foundation ECN. This report presents the selection of the most appropriate codes. To cover the range of relevant accidents, a suite of three codes is recommended for analyses of HTR-M and MHTGR reactors. (orig.).

  4. Visual and intelligent transients and accidents analyzer based on thermal-hydraulic system code

    International Nuclear Information System (INIS)

    Meng Lin; Rui Hu; Yun Su; Ronghua Zhang; Yanhua Yang

    2005-01-01

    Full text of publication follows: Many thermal-hydraulic system codes were developed in the past twenty years, such as RELAP5, RETRAN, ATHLET, etc. Because of their general and advanced features in thermal-hydraulic computation, they are widely used in the world to analyze transients and accidents. But there are following disadvantages for most of these original thermal-hydraulic system codes. Firstly, because models are built through input decks, so the input files are complex and non-figurative, and the style of input decks is various for different users and models. Secondly, results are shown in off-line data file form. It is not convenient for analysts who may pay more attention to dynamic parameters trend and changing. Thirdly, there are few interfaces with other program in these original thermal-hydraulic system codes. This restricts the codes expanding. The subject of this paper is to develop a powerful analyzer based on these thermal-hydraulic system codes to analyze transients and accidents more simply, accurately and fleetly. Firstly, modeling is visual and intelligent. Users build the thermalhydraulic system model using component objects according to their needs, and it is not necessary for them to face bald input decks. The style of input decks created automatically by the analyzer is unified and can be accepted easily by other people. Secondly, parameters concerned by analyst can be dynamically communicated to show or even change. Thirdly, the analyzer provide interface with other programs for the thermal-hydraulic system code. Thus parallel computation between thermal-hydraulic system code and other programs become possible. In conclusion, through visual and intelligent method, the analyzer based on general and advanced thermal-hydraulic system codes can be used to analysis transients and accidents more effectively. The main purpose of this paper is to present developmental activities, assessment and application results of the visual and intelligent

  5. Current and anticipated uses of thermal hydraulic codes at the Japan Atomic Energy Research Institute

    International Nuclear Information System (INIS)

    Akimoto, Hajime; Kukita; Ohnuki, Akira

    1997-01-01

    The Japan Atomic Energy Research Institute (JAERI) is conducting several research programs related to thermal-hydraulic and neutronic behavior of light water reactors (LWRs). These include LWR safety research projects, which are conducted in accordance with the Nuclear Safety Commission's research plan, and reactor engineering projects for the development of innovative reactor designs or core/fuel designs. Thermal-hydraulic and neutronic codes are used for various purposes including experimental analysis, nuclear power plant (NPP) safety analysis, and design assessment

  6. Research on the improvement of nuclear safety -Thermal hydraulic tests for reactor safety system-

    Energy Technology Data Exchange (ETDEWEB)

    Jung, Moon Kee; Park, Choon Kyung; Yang, Sun Kyoo; Chun, Se Yung; Song, Chul Hwa; Jun, Hyung Kil; Jung, Heung Joon; Won, Soon Yun; Cho, Yung Roh; Min, Kyung Hoh; Jung, Jang Hwan; Jang, Suk Kyoo; Kim, Bok Deuk; Kim, Wooi Kyung; Huh, Jin; Kim, Sook Kwan; Moon, Sang Kee; Lee, Sang Il [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1995-06-01

    The present research aims at the development of the thermal hydraulic verification test technology for the safety system of the conventional and advanced nuclear power plant and the development of the advanced thermal hydraulic measuring techniques. In this research, test facilities simulating the primary coolant system and safety system are being constructed for the design verification tests of the existing and advanced nuclear power plant. 97 figs, 14 tabs, 65 refs. (Author).

  7. Pharmacy Students' Attitudes Toward Death and End-of-life Care

    Science.gov (United States)

    Broeseker, Amy E.

    2010-01-01

    Objectives To assess pharmacy students' attitudes toward death and end-of-life care. Methods Third-year pharmacy students enrolled in the Ethics in Christianity and Health Care course were administered a survey instrument prior to introduction of the topic of end-of-life care. Students' attitudes toward different professions' roles in end-of-life care and their comfort in discussing end-of-life issues were assessed. The survey instrument was readministered to the same students at the end of their fourth year. Results On most survey items, female students responded more favorably toward death and end-of-life care than male students. One exception was the perceived emotional ability to be in the room of a dying patient or loved one. Post-experiential survey responses were generally more favorable toward death and end-of-life care than were pre-discussion responses. Conclusions In general, when surveyed concerning death and end-of-life care, female students responded more favorably than male students, and responses at the end of the fourth year were more favorable than at the beginning of the course. PMID:21045946

  8. End of life care preferences among people of advanced age: LiLACS NZ.

    Science.gov (United States)

    Gott, Merryn; Frey, Rosemary; Wiles, Janine; Rolleston, Anna; Teh, Ruth; Moeke-Maxwell, Tess; Kerse, Ngaire

    2017-12-19

    Understanding end of life preferences amongst the oldest old is crucial to informing appropriate palliative and end of life care internationally. However, little has been reported in the academic literature about the end of life preferences of people in advanced age, particularly the preferences of indigenous older people, including New Zealand Māori. Data on end of life preferences were gathered from 147 Māori (aged >80 years) and 291 non- Māori aged (>85 years), during three waves of Te Puawaitangi O Nga Tapuwae Kia Ora Tonu, Life and Living in Advanced Age (LiLACs NZ). An interviewer-led questionnaire using standardised tools and including Māori specific subsections was used. The top priority for both Māori and non-Māori participants at end of life was 'not being a burden to my family'. Interestingly, a home death was not a high priority for either group. End of life preferences differed by gender, however these differences were culturally contingent. More female Māori participants wanted spiritual practices at end of life than male Māori participants. More male non-Māori participants wanted to be resuscitated than female non- Māori participants. That a home death was not in the top three end of life priorities for our participants is not consistent with palliative care policy in most developed countries where place of death, and particularly home death, is a central concern. Conversely our participants' top concern - namely not being a burden - has received little research or policy attention. Our results also indicate a need to pay attention to diversity in end of life preferences amongst people of advanced age, as well as the socio-cultural context within which preferences are formulated.

  9. A flexible coupling scheme for Monte Carlo and thermal-hydraulics codes

    Energy Technology Data Exchange (ETDEWEB)

    Hoogenboom, J. Eduard, E-mail: J.E.Hoogenboom@tudelft.nl [Delft University of Technology (Netherlands); Ivanov, Aleksandar; Sanchez, Victor, E-mail: Aleksandar.Ivanov@kit.edu, E-mail: Victor.Sanchez@kit.edu [Karlsruhe Institute of Technology, Institute of Neutron Physics and Reactor Technology, Eggenstein-Leopoldshafen (Germany); Diop, Cheikh, E-mail: Cheikh.Diop@cea.fr [CEA/DEN/DANS/DM2S/SERMA, Commissariat a l' Energie Atomique, Gif-sur-Yvette (France)

    2011-07-01

    A coupling scheme between a Monte Carlo code and a thermal-hydraulics code is being developed within the European NURISP project for comprehensive and validated reactor analysis. The scheme is flexible as it allows different Monte Carlo codes and different thermal-hydraulics codes to be used. At present the MCNP and TRIPOLI4 Monte Carlo codes can be used and the FLICA4 and SubChanFlow thermal-hydraulics codes. For all these codes only an original executable is necessary. A Python script drives the iterations between Monte Carlo and thermal-hydraulics calculations. It also calls a conversion program to merge a master input file for the Monte Carlo code with the appropriate temperature and coolant density data from the thermal-hydraulics calculation. Likewise it calls another conversion program to merge a master input file for the thermal-hydraulics code with the power distribution data from the Monte Carlo calculation. Special attention is given to the neutron cross section data for the various required temperatures in the Monte Carlo calculation. Results are shown for an infinite lattice of PWR fuel pin cells and a 3 x 3 fuel BWR pin cell cluster. Various possibilities for further improvement and optimization of the coupling system are discussed. (author)

  10. Development of MARS for multi-dimensional and multi-purpose thermal-hydraulic system analysis

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Won Jae; Chung, Bub Dong; Kim, Kyung Doo; Hwang, Moon Kyu; Jeong, Jae Jun; Ha, Kwi Seok; Joo, Han Gyu [Korea Atomic Energy Research Institute, T/H Safety Research Team, Yusung, Daejeon (Korea)

    2000-10-01

    MARS (Multi-dimensional Analysis of Reactor Safety) code is being developed by KAERI for the realistic thermal-hydraulic simulation of light water reactor system transients. MARS 1.4 has been developed as a final version of basic code frame for the multi-dimensional analysis of system thermal-hydraulics. Since MARS 1.3, MARS 1.4 has been improved to have the enhanced code capability and user friendliness through the unification of input/output features, code models and code functions, and through the code modernization. Further improvements of thermal-hydraulic models, numerical method and user friendliness are being carried out for the enhanced code accuracy. As a multi-purpose safety analysis code system, a coupled analysis system, MARS/MASTER/CONTEMPT, has been developed using multiple DLL (Dynamic Link Library) techniques of Windows system. This code system enables the coupled, that is, more realistic analysis of multi-dimensional thermal-hydraulics (MARS 2.0), three-dimensional core kinetics (MASTER) and containment thermal-hydraulics (CONTEMPT). This paper discusses the MARS development program, and the developmental progress of the MARS 1.4 and the MARS/MASTER/CONTEMPT focusing on major features of the codes and their verification. It also discusses thermal hydraulic models and new code features under development. (author)

  11. Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 1

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    More than 100 papers were presented. The meeting was divided in 56 sessions and covered the following topics: Plant Operation, Retrofitting and Maintenance Experience; Steam Generator Operation and Maintenance; Artificial Intelligence and Expert Systems; Seismic Technologies for Plant Design and Operations; Aging Management and Life Extension; Two-Phase Flow Modeling and Applications; Severe Accidents and Degraded Core Thermal Hydraulics; Plant Simulators, Analyzers, and Workstations; Advanced Nuclear Fuel Challenges; Recent Nuclear Power Station Decommissioning Experiences in the USA; Application of Probabilistic risk assessment/Probabilistic safety assessment (PRA/PSA) in Design and Modification; Numerical Modeling in Thermal Hydraulics; General Thermal Hydraulics; Severe Accident Management; Licensing and Regulatory Requirements; Advanced Light Water Reactor Designs to Support Reduced Emergency Planning; Best Estimate loss-of-coolant (LOCA) Methodologies; Plant Instrumentation and Control; LWR Fuel Designs for Improved Thermal Hydraulic Performance; Performance Assessment of Radioactive Waste Disposal; Thermal Hydraulics in Passive Reactor Systems; Advances in Man-Machine Interface Design and the Related Human Factors Engineering; Advances in Measurements and Instrumentation; Computer Aided Technology for non-destructive evaluation (NDE) and Plant Maintenance Plant Uprating; Flow-Accelerated Corrosion in Nuclear Power Plants; Advances in Radiological Measurement and Analysis Risk Management and Assessment; Stability in Thermal Hydraulic Systems; Critical heat flux (CHF) and Post Dryout Heat Transfer; Plant Transient and Accident Modeling.

  12. Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 1

    International Nuclear Information System (INIS)

    2004-01-01

    More than 100 papers were presented. The meeting was divided in 56 sessions and covered the following topics: Plant Operation, Retrofitting and Maintenance Experience; Steam Generator Operation and Maintenance; Artificial Intelligence and Expert Systems; Seismic Technologies for Plant Design and Operations; Aging Management and Life Extension; Two-Phase Flow Modeling and Applications; Severe Accidents and Degraded Core Thermal Hydraulics; Plant Simulators, Analyzers, and Workstations; Advanced Nuclear Fuel Challenges; Recent Nuclear Power Station Decommissioning Experiences in the USA; Application of Probabilistic risk assessment/Probabilistic safety assessment (PRA/PSA) in Design and Modification; Numerical Modeling in Thermal Hydraulics; General Thermal Hydraulics; Severe Accident Management; Licensing and Regulatory Requirements; Advanced Light Water Reactor Designs to Support Reduced Emergency Planning; Best Estimate loss-of-coolant (LOCA) Methodologies; Plant Instrumentation and Control; LWR Fuel Designs for Improved Thermal Hydraulic Performance; Performance Assessment of Radioactive Waste Disposal; Thermal Hydraulics in Passive Reactor Systems; Advances in Man-Machine Interface Design and the Related Human Factors Engineering; Advances in Measurements and Instrumentation; Computer Aided Technology for non-destructive evaluation (NDE) and Plant Maintenance Plant Uprating; Flow-Accelerated Corrosion in Nuclear Power Plants; Advances in Radiological Measurement and Analysis Risk Management and Assessment; Stability in Thermal Hydraulic Systems; Critical heat flux (CHF) and Post Dryout Heat Transfer; Plant Transient and Accident Modeling

  13. Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2004-07-01

    More than 100 papers presented at the meeting were divided in 56 sessions and covered the following topics: Plant Operation, Retrofitting and Maintenance Experience; Steam Generator Operation and Maintenance; Artificial Intelligence and Expert Systems; Seismic Technologies for Plant Design and Operations; Aging Management and Life Extension; Two-Phase Flow Modeling and Applications; Severe Accidents and Degraded Core Thermal Hydraulics; Plant Simulators, Analyzers, and Workstations; Advanced Nuclear Fuel Challenges; Recent Nuclear Power Station Decommissioning Experiences in the USA; Application of Probabilistic risk assessment/Probabilistic safety assessment (PRA/PSA) in Design and Modification; Numerical Modeling in Thermal Hydraulics; General Thermal Hydraulics; Severe Accident Management; Licensing and Regulatory Requirements; Advanced Light Water Reactor Designs to Support Reduced Emergency Planning; Best Estimate loss-of-coolant (LOCA) Methodologies; Plant Instrumentation and Control; LWR Fuel Designs for Improved Thermal Hydraulic Performance; Performance Assessment of Radioactive Waste Disposal; Thermal Hydraulics in Passive Reactor Systems; Advances in Man-Machine Interface Design and the Related Human Factors Engineering; Advances in Measurements and Instrumentation; Computer Aided Technology for non-destructive evaluation (NDE) and Plant Maintenance Plant Uprating; Flow-Accelerated Corrosion in Nuclear Power Plants; Advances in Radiological Measurement and Analysis Risk Management and Assessment; Stability in Thermal Hydraulic Systems; Critical heat flux (CHF) and Post Dryout Heat Transfer; Plant Transient and Accident Modeling.

  14. Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 2

    International Nuclear Information System (INIS)

    2004-01-01

    More than 100 papers presented at the meeting were divided in 56 sessions and covered the following topics: Plant Operation, Retrofitting and Maintenance Experience; Steam Generator Operation and Maintenance; Artificial Intelligence and Expert Systems; Seismic Technologies for Plant Design and Operations; Aging Management and Life Extension; Two-Phase Flow Modeling and Applications; Severe Accidents and Degraded Core Thermal Hydraulics; Plant Simulators, Analyzers, and Workstations; Advanced Nuclear Fuel Challenges; Recent Nuclear Power Station Decommissioning Experiences in the USA; Application of Probabilistic risk assessment/Probabilistic safety assessment (PRA/PSA) in Design and Modification; Numerical Modeling in Thermal Hydraulics; General Thermal Hydraulics; Severe Accident Management; Licensing and Regulatory Requirements; Advanced Light Water Reactor Designs to Support Reduced Emergency Planning; Best Estimate loss-of-coolant (LOCA) Methodologies; Plant Instrumentation and Control; LWR Fuel Designs for Improved Thermal Hydraulic Performance; Performance Assessment of Radioactive Waste Disposal; Thermal Hydraulics in Passive Reactor Systems; Advances in Man-Machine Interface Design and the Related Human Factors Engineering; Advances in Measurements and Instrumentation; Computer Aided Technology for non-destructive evaluation (NDE) and Plant Maintenance Plant Uprating; Flow-Accelerated Corrosion in Nuclear Power Plants; Advances in Radiological Measurement and Analysis Risk Management and Assessment; Stability in Thermal Hydraulic Systems; Critical heat flux (CHF) and Post Dryout Heat Transfer; Plant Transient and Accident Modeling

  15. A flexible coupling scheme for Monte Carlo and thermal-hydraulics codes

    International Nuclear Information System (INIS)

    Hoogenboom, J. Eduard; Ivanov, Aleksandar; Sanchez, Victor; Diop, Cheikh

    2011-01-01

    A coupling scheme between a Monte Carlo code and a thermal-hydraulics code is being developed within the European NURISP project for comprehensive and validated reactor analysis. The scheme is flexible as it allows different Monte Carlo codes and different thermal-hydraulics codes to be used. At present the MCNP and TRIPOLI4 Monte Carlo codes can be used and the FLICA4 and SubChanFlow thermal-hydraulics codes. For all these codes only an original executable is necessary. A Python script drives the iterations between Monte Carlo and thermal-hydraulics calculations. It also calls a conversion program to merge a master input file for the Monte Carlo code with the appropriate temperature and coolant density data from the thermal-hydraulics calculation. Likewise it calls another conversion program to merge a master input file for the thermal-hydraulics code with the power distribution data from the Monte Carlo calculation. Special attention is given to the neutron cross section data for the various required temperatures in the Monte Carlo calculation. Results are shown for an infinite lattice of PWR fuel pin cells and a 3 x 3 fuel BWR pin cell cluster. Various possibilities for further improvement and optimization of the coupling system are discussed. (author)

  16. Development of MARS for multi-dimensional and multi-purpose thermal-hydraulic system analysis

    International Nuclear Information System (INIS)

    Lee, Won Jae; Chung, Bub Dong; Kim, Kyung Doo; Hwang, Moon Kyu; Jeong, Jae Jun; Ha, Kwi Seok; Joo, Han Gyu

    2000-01-01

    MARS (Multi-dimensional Analysis of Reactor Safety) code is being developed by KAERI for the realistic thermal-hydraulic simulation of light water reactor system transients. MARS 1.4 has been developed as a final version of basic code frame for the multi-dimensional analysis of system thermal-hydraulics. Since MARS 1.3, MARS 1.4 has been improved to have the enhanced code capability and user friendliness through the unification of input/output features, code models and code functions, and through the code modernization. Further improvements of thermal-hydraulic models, numerical method and user friendliness are being carried out for the enhanced code accuracy. As a multi-purpose safety analysis code system, a coupled analysis system, MARS/MASTER/CONTEMPT, has been developed using multiple DLL (Dynamic Link Library) techniques of Windows system. This code system enables the coupled, that is, more realistic analysis of multi-dimensional thermal-hydraulics (MARS 2.0), three-dimensional core kinetics (MASTER) and containment thermal-hydraulics (CONTEMPT). This paper discusses the MARS development program, and the developmental progress of the MARS 1.4 and the MARS/MASTER/CONTEMPT focusing on major features of the codes and their verification. It also discusses thermal hydraulic models and new code features under development. (author)

  17. Embracing a broad spirituality in end of life discussions and advance care planning.

    Science.gov (United States)

    Churchill, Larry R

    2015-04-01

    Advance care planning for end of life typically focuses on the mechanics of completing living wills and durable power of attorney documents. Even when spiritual aspects of end of life care are discussed, the dominant assumptions are those of traditional religious systems. A broad view of spirituality is needed, one that may involve traditional religious beliefs but also includes personal understandings of what is holy or sacred. Embracing this broad practice of spirituality will help both familial and professional caregivers honor an essential aspect of end of life discussions and promote greater discernment of the deep meaning in advance care documents.

  18. American Society for Pain Management Nursing position statement: pain management at the end of life.

    Science.gov (United States)

    Reynolds, Janice; Drew, Debra; Dunwoody, Colleen

    2013-09-01

    Pain at the end of life continues to be of great concern as it may be unrecognized or untreated. While nurses have an ethical obligation to reduce suffering at the end of life, barriers remain regarding appropriate and adequate pain management at the end of life. This position statement from the American Society for Pain Management Nursing contains recommendations for nurses, prescribers, and institutions that would improve pain management for this vulnerable population. Copyright © 2013 American Society for Pain Management Nursing. Published by Elsevier Inc. All rights reserved.

  19. Determination of thermal-hydraulic loads on reactor internals in a DBA-situation

    International Nuclear Information System (INIS)

    Ville Lestinen; Timo Toppila

    2005-01-01

    Full text of publication follows: According to Finnish regulatory requirements, reactor internals have to stay intact in a design basis accident (DBA) situation, so that control rods can still penetrate into the core. To fulfill this demand some criteria must be followed in periodical in-service inspections. This is the motivation for studying and developing more detailed methods for analysis of thermal-hydraulic loads on reactor internals during the DBA-situation for the Loviisa NPP in Finland. The objective of this research program is to connect thermal-hydraulic and mechanical analysis methods with the goal to produce a reliable method for determination of thermal-hydraulic and mechanical loads on reactor internals in the accident situation. The tools studied are thermal-hydraulic system codes, computational fluid dynamics (CFD) codes and finite element analysis (FEA) codes. This paper concentrates mainly on thermal-hydraulic part of the research, but also the mechanical aspects are discussed. Firstly, the paper includes a short literary review of the available methods to analyse the described problem including both thermal-hydraulic and structural analysis parts. Secondly, different possibilities to carry out thermal-hydraulic analyses have been studied. The DBA-case includes complex physical phenomena and therefore modelling is difficult. The accident situation can be for example LLOCA. When the pipe has broken, the pressure decreases and water starts to evaporate, which consumes energy and that way limits the pressure decrease. After some period of time, the system reaches a new equilibrium state. To perform exact thermal-hydraulic analysis also two phase phenomena must be included. Therefore CFD codes are not capable of modelling the DBA situation very well, but the use of CFD codes requires that the effect of two phase flow must be added somehow. One method to calculate two phase phenomena with CFD codes is to use thermal-hydraulic system codes to calculate

  20. Thermal hydraulic feasibility analysis of the IBED PHTS for ITER

    Energy Technology Data Exchange (ETDEWEB)

    Carloni, Dario, E-mail: dacarloni@gmail.com [Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, Pisa University, Via Diotisalvi 2, 56126 Pisa (Italy); Dell’Orco, Giovanni; Babulal, Gopalapillai; Somboli, Fabio; Serio, Luigi [ITER Organisation, Route de Vinon sur Verdon, 13115 Saint Paul Lez Durance (France); Paci, Sandro [Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, Pisa University, Via Diotisalvi 2, 56126 Pisa (Italy)

    2013-10-15

    One of the main challenges of the ITER fusion reactor is to effectively remove large amount of heat deposited to the surface of the plasma facing components. The tokamak cooling water system (TCWS) will accomplish the objective of removing about 1 GW of peak heat load from in-vessel components while maintaining pressures and temperatures of the coolant within acceptable and safe limits during different operational scenarios. A study of feasibility has been launched for the IBED PHTS (Integrated Blanket, Edge localized mode coils (ELMs) and Divertor Primary Heat Transfer System; it consists of five independent cooling trains (four operational and one in stand-by), one steam pressurizer, supply and return headers, ring manifolds and connections to the all in-vessel components (i.e. First Wall Blanket, Divertor, ELM, Diagnostics and other Ports clients). The dynamic behaviour of the IBED PHTS has been investigated by means of RELAP5{sup ®} code to simulate the response of the system during plasma pulse and baking operations. Due to the plasma heat deposition on the surfaces of the in-vessel components and subsequent increase in hot leg temperature, a large amount of water volume is transferred from the hot legs of the circuit to the surge-line of the pressurizer during each burn cycle. This causes rapid increase of pressure and temperature of the system and the following actions are proposed to counteract these variations: spray injection in the upper dome of the pressurizer from the Chemical and Volume Control System (CVCS) to reduce the pressure and active control of flow rates through heat exchangers and their bypass loops to regulate the heat transfer from the primary system to the environment via secondary and tertiary loops. This paper focuses on the prediction of the thermal hydraulic behaviour of the IBED PHTS during plasma pulses and baking scenarios, describing the various activity of the analysis, the geometrical assessment of the circuit and the modelling

  1. Artificial Nutrition (Food) and Hydration (Fluids) at the End of Life

    Science.gov (United States)

    Artificial Nutrition (Food) and Hydration (Fluids) at the End of Life It is very common for doctors to provide ... or recovering from surgery. This is called “artificial nutrition and hydration” and like all medical treatments, it ...

  2. End-of-life training for paid carers working with people with learning disabilities.

    Science.gov (United States)

    Codling, Mary; Knowles, Jane; Vevers, Ann

    2014-04-01

    People with learning disabilities are living longer lives. Over the past few years, research has explored the needs of people with learning disabilities, their families and learning disability professionals in relation to end-of-life care and death. However, little is known about the needs of paid carers and their experience of end-of-life care. This article discusses the development, implementation and evaluation of a study day about end-of-life care that was delivered to paid carers on two separate occasions in Berkshire Healthcare NHS Foundation Trust. A total of 43 paid carers attended and the days were well evaluated. The need for further training for paid carers who work with people with learning disabilities at the end of life was highlighted.

  3. End-of-Life Indicators for NIMA's High-Performance Cesium Frequency Standards

    National Research Council Canada - National Science Library

    Brock, C; Tolman, B. W; Taylor, R. E

    2002-01-01

    .... The mean lifetime of the cesium-beam tube (CBT) is approximately 6 years; failure or end-of-life of the CBT is a significant cause in the reduction of data used to produce the NIMA GPS precise ephemeris...

  4. Communication Matters: Exploring the Intersection of Family and Practitioner End of Life Communication

    Directory of Open Access Journals (Sweden)

    Leah M. Omilion-Hodges

    2017-03-01

    Full Text Available After establishing a baseline understanding of some of the factors that influence and shape family end of life communication, empirical research centered on the communication tendencies of nationally-recognized palliative care clinicians is presented. Because death is no longer confined to the bedroom and individuals are increasingly turning to hospitals and health care institutes to assist with end of life, the role of palliative care practitioners is vital. To that end, common communication-rooted issues that may transpire among various medical personnel are explored. Focus on a shared underlying tension—care vs. cure—links the findings between family and palliative care clinician communication regarding end of life. Practical communication solutions and suggestions are offered to facilitate productive and mindful end of life communication between and among family members and health care practitioners.

  5. Graduate Students' Reflections on Elder and End-of-Life Care for Prisoners.

    Science.gov (United States)

    Baumann, Steven L; Todaro-Franceschi, Vidette

    2017-07-01

    The focus of this report was graduate nursing students' reflections on elder and end-of-life care for prisoners. The personal reflections of 21 graduate nursing students who attended a presentation by Susan J. Loeb on October 26, 2016 were included in this report. The title of the presentation was "Enhancing End-of-Life Care for Prisoners Through Partnering With the Prison Community." The student essays were synthesized to construct a summary essay, from which four themes were identified: aging in prison, dying in prison, ethical and professional issues in the elder and end-of-life care of prisoners, and ethical and professional issues in research involving elderly and end-of-life care of prisoners. These findings were interpreted from a global perspective in light of two different nursing perspectives: the humanbecoming tradition and the science of unitary human beings.

  6. How Can an Emergency Department Assist Patients and Caregivers at the End of Life?

    Science.gov (United States)

    ... And Caregivers At The End Of Life? How Can An Emergency Department Assist Patients And Caregivers At ... your family. Five ways that the Emergency Department can help 1. Assist in the recognition and understanding ...

  7. Hospital executive leadership: a critical component for improving care at the end of life.

    Science.gov (United States)

    Cooney, James P; Landers, Glenn M; Williams, Julianna M

    2002-01-01

    End-of-life care and its planning by individuals, in concert with their families and professional healthcare givers, pose important social, legal, and ethical issues. The authors evaluate the results of a multi-year (1997-2001) collaborative effort among representatives of Georgia healthcare providers, healthcare payers, and the general public that was designed to (a) improve end-of-life care through a community-focused field effort to increase public awareness, execution, and institutional management of advance directives and (b) impact institutional and state government systems and policies around end-of-life care. The authors conclude that a proactive presence of senior management is integral in implementing systematic change in hospital-based end-of-life care and offer practical recommendations to hospital leaders to affect real change in their institutions.

  8. Training Providers and Patients to Talk about End-of-Life Care

    Science.gov (United States)

    Failing to discuss the transition from active cancer treatment to end-of-life care can leave doctors unsure of what a patient truly wants. Failing to receive end-of-life care in line with their values and wishes can cause patients and their families great distress. Researchers have developed innovative, evidence-based programs to help doctors and patients improve their communication skills and grow comfortable with these discussions.

  9. Oncologists' strategies and barriers to effective communication about the end of life.

    Science.gov (United States)

    Granek, Leeat; Krzyzanowska, Monika K; Tozer, Richard; Mazzotta, Paolo

    2013-07-01

    Communicating about the end of life with patients has been reported as one of the most difficult and stressful part of the work of oncologists. Despite this fact, oncologists receive little training in this area, and many do not communicate effectively with patients. The purpose of this analysis, part of a larger study examining oncologists' experiences of patient loss, was to explore oncologists' communication strategies and communication barriers when discussing end-of-life issues with patients. Twenty oncologists were interviewed at three hospitals about their communication strategies on end-of-life issues with patients. The data were analyzed using the grounded theory method. The findings revealed the strategies to effective communication about the end of life included: being open and honest; having ongoing, early conversations; communicating about modifying treatment goals; and balancing hope and reality. Barriers to implementing these strategies fell broadly into three domains, including physician factors, patient factors, and institutional factors. Physician factors included difficulty with treatment and palliation, personal discomfort with death and dying, diffusion of responsibility among colleagues, using the "death-defying mode," lack of experience, and lack of mentorship. Patient factors included, patients and/or families being reluctant to talk about the end of life, language barriers, and younger age. Institutional factors included stigma around palliative care, lack of protocol about end-of-life issues; and lack of training for oncologists on how to talk with patients about end-of-life issues. We conclude by drawing implications from our study and suggest that further research and intervention are necessary to aid oncologists in achieving effective communication about end-of-life issues.

  10. [Organising and supporting the end of life when faced with a refusal of care].

    Science.gov (United States)

    Rautureau, Pascal

    2018-04-01

    Often ethically complex, end-of-life situations can mean nursing teams are confronted with a refusal of care. Through a representative clinical situation, a nurse describes the support provided by a multidisciplinary team, in the home, to comply with the wishes of a person at the end of life, support the family, anticipate possible difficulties and organise adapted care which respects all those concerned. Copyright © 2018 Elsevier Masson SAS. All rights reserved.

  11. Neutronics and thermal-hydraulics analysis of KUHFR

    Energy Technology Data Exchange (ETDEWEB)

    Woodruff, W L [Argonne National Laboratory, Argonne, IL (United States); Mishima, K [KURRI, Osaka (Japan)

    1983-08-01

    control rod worth with reduced enrichment has not yet determined, but only a small decrease in worth is expected. These BOL boron poisoned fuels are also used as the fresh fuel feed for the equilibrium fuel cycle studies contained in this report. The first three cases shown have matching cycle lengths in the equilibrium cycle, while the last case has a considerably longer cycle length. These results are similarly reflected in the 'Maximum Cycle Lengths' shown for unpoisoned BOL cores. Thus, the first three case can be considered comparable. The last case might be considered as an option for an extended cycle length design. The cycle length for this case is increased by about 21%. Obviously, by decreasing the uranium density in the fuel meat (to 2.7 g/cm{sup 3}), the cycle length for this design could be reduced to match that of the other cases. Thermal-hydraulic calculations have been carried out in order to study the safety aspects of the use of reduced enrichment uranium fuel for the KUHFR. The calculations were based on what is outlined in the Safety Analysis Report for the KUHFR and also the IAEA Guidebook for the RERTR program. Only a few combinations of hydraulic parameters have been tested because the reactor safety cannot be discussed without any nuclear physics considerations. For example, any variations in fuel coolant channels may change not only flow velocities but also power peaking factors which may affect the assessment of reactor safety. For this reason, the thermal-hydraulic calculations were carried out only for those specific cases on which neutronics analysis has been already performed. Low enriched uranium (LEU) cases are also included in this study as initial feasibility studies for potential conversion. The computer code PLTEMP has been developed to calculate the flow distribution in the core, fuel plate temperatures and DNB heat fluxes.

  12. Allowing Family to be Family: End-of-Life Care in Veterans Affairs Medical Foster Homes.

    Science.gov (United States)

    Manheim, Chelsea E; Haverhals, Leah M; Jones, Jacqueline; Levy, Cari R

    2016-01-01

    The Medical Foster Home program is a unique long-term care program coordinated by the Veterans Health Administration. The program pairs Veterans with private, 24-hour a day community-based caregivers who often care for Veterans until the end of life. This qualitative study explored the experiences of care coordination for Medical Foster Home Veterans at the end of life with eight Veterans' family members, five Medical Foster Home caregivers, and seven Veterans Health Administration Home-Based Primary Care team members. A case study, qualitative content analysis identified these themes addressing care coordination and impact of the Medical Foster Home model on those involved: (a) Medical Foster Home program supports Veterans' families; (b) Medical Foster Home program supports the caregiver as family; (c) Veterans' needs are met socially and culturally at the end of life; and (d) the changing needs of Veterans, families, and caregivers at Veterans' end of life are addressed. Insights into how to best support Medical Foster Home caregivers caring for Veterans at the end of life were gained including the need for more and better respite options and how caregivers are compensated in the month of the Veteran's death, as well as suggestions to navigate end-of-life care coordination with multiple stakeholders involved.

  13. Diabetes and end of life: ethical and methodological issues in gathering evidence to guide care.

    Science.gov (United States)

    Dunning, Trisha; Duggan, Nicole; Savage, Sally; Martin, Peter

    2013-03-01

    Providing palliative care for people with diabetes at the end of life is part of the chronic disease care trajectory, but end of life care is complex and the presence of diabetes further complicates management. The aim of the paper is to discuss the ethical and methodological issues encountered when undertaking research to develop guidelines for managing diabetes at the end of life and the strategies used to address the issues. The issues emerged as we developed guidelines for managing diabetes at the end of life, which included conducting individual interviews with 14 people with diabetes requiring palliative care and 10 family members. A reflexive researcher journal was maintained throughout the guideline development process. The interview transcripts and researcher's journal were analysed to determine key methodological, ethical and researcher-related issues. Key themes were vulnerability of the sampling population, methodological issues included recruiting participants and ensuring rigor, ethical issues concerned benefit and risk, justice, autonomy, privacy, professional boundaries and informed consent. Researcher-related issues were identified such as managing participant distress and their own emotional distress. People were willing to discuss end of life diabetes management preferences. Undertaking research with people at the end of life is complex because of their vulnerability and the ethical issues involved. However, the ethical principles of autonomy and justice apply and people should be given the relevant information and opportunity to decide whether to participate or not. © 2012 The Authors. Scandinavian Journal of Caring Sciences © 2012 Nordic College of Caring Science.

  14. Pin clad strains in Phenix

    International Nuclear Information System (INIS)

    Languille, A.

    1979-07-01

    The Phenix reactor has operated for 4 years in a satisfactory manner. The first 2 sub-assembly loadings contained pins clad in solution treated 316. The principal pin strains are: diametral strain (swelling and irradiation creep), ovality and spiral bending of the pin (interaction of wire and pin cluster and wrapper). A pin cluster irradiated to a dose of 80 dpa F reached a pin diameter strain of 5%. This strain is principally due to swelling (low fission gas pressure). The principal parameters governing the swelling are instantaneous dose, time and temperature for a given type of pin cladding. Other types of steel are or will be irradiated in Phenix. In particular, cold-worked titanium stabilised 316 steel should contribute towards a reduction in the pin clad strains and increase the target burn-up in this reactor. (author)

  15. The Phenix Detector magnet subsystem

    International Nuclear Information System (INIS)

    Yamamoto, R.M.; Bowers, J.M.; Harvey, A.R.

    1995-01-01

    The PHENIX [Photon Electron New Heavy Ion Experiment] Detector is one of two large detectors presently under construction for RHIC (Relativistic Heavy Ion Collider) located at Brookhaven National Laboratory. Its primary goal is to detect a new phase of matter; the quark-gluon plasma. In order to achieve this objective, the PHENIX Detector utilizes a complex magnet subsystem which is comprised of two large magnets identified as the Central Magnet (CM) and the Muon Magnet (MM). Muon Identifier steel is also included as part of this package. The entire magnet subsystem stands over 10 meters tall and weighs in excess of 1900 tons (see Fig. 1). Magnet size alone provided many technical challenges throughout the design and fabrication of the project. In addition, interaction with foreign collaborators provided the authors with new areas to address and problems to solve. Russian collaborators would fabricate a large fraction of the steel required and Japanese collaborators would supply the first coil. This paper will describe the overall design of the PHENIX magnet subsystem and discuss its present fabrication status

  16. The sPHENIX Experiment

    Science.gov (United States)

    Pérez Lara, Carlos E.

    2018-02-01

    Our understanding of QCD under extreme conditions has advanced tremendously in the last 20 years with the discovery of the Quark Gluon Plasma and its characterisation in heavy ion collisions at RHIC and LHC. The sPHENIX detector planned at RHIC is designed to further study the microscopic nature of the QGP through precision measurements of jet, upsilon and open heavy flavor probes over a broad pT range. The multi-year sPHENIX physics program will commence in early 2023, using state-of-the art detector technologies to fully exploit the highest RHIC luminosities. The experiment incorporates the 1.4 T former BaBar solenoid magnet, and will feature high precision tracking and vertexing capabilities, provided by a compact TPC, Si-strip intermediate tracker and MAPS vertex detector. This is complemented by highly granular electromagnetic and hadronic calorimetry with full azimuthal coverage. In this document I describe the sPHENIX detector design and physics program, with particular emphasis on the comprehensive open heavy flavour program enabled by the experiment's large coverage, high rate capability and precision vertexing.

  17. The Phenix Detector magnet subsystem

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, R.M.; Bowers, J.M.; Harvey, A.R. [Lawrence Livermore National Lab., CA (United States)] [and others

    1995-05-19

    The PHENIX [Photon Electron New Heavy Ion Experiment] Detector is one of two large detectors presently under construction for RHIC (Relativistic Heavy Ion Collider) located at Brookhaven National Laboratory. Its primary goal is to detect a new phase of matter; the quark-gluon plasma. In order to achieve this objective, the PHENIX Detector utilizes a complex magnet subsystem which is comprised of two large magnets identified as the Central Magnet (CM) and the Muon Magnet (MM). Muon Identifier steel is also included as part of this package. The entire magnet subsystem stands over 10 meters tall and weighs in excess of 1900 tons (see Fig. 1). Magnet size alone provided many technical challenges throughout the design and fabrication of the project. In addition, interaction with foreign collaborators provided the authors with new areas to address and problems to solve. Russian collaborators would fabricate a large fraction of the steel required and Japanese collaborators would supply the first coil. This paper will describe the overall design of the PHENIX magnet subsystem and discuss its present fabrication status.

  18. Status and subjects of thermal-hydraulic analysis for next-generation LWRs

    International Nuclear Information System (INIS)

    2000-03-01

    The status and subjects on thermal-hydraulic analysis for next-generation light water reactors (LWRs) with passive safety systems were surveyed through about 5 years until March 1999 by subcommittee on improvement of reactor thermal-hydraulic analysis codes under the nuclear code committee in Japan Atomic Energy Research Institute. Based on the survey results and discussion, the status and subjects on system analysis for various types of proposed reactor were summarized in 1998 and those on multidimensional two-phase flow analysis were also reviewed, since the multidimensional analysis was recognized as one of the most important subjects through the investigation on system analysis. In this report, the status and subjects for the following were summarized from the survey results and discussion in 1998 and 1999; (1) BWR neutronic/thermal-hydraulic coupled analysis, (2) Evaluation of passive safety system performance and (3) Gas-liquid two-phase flow analysis. The contents in this report are the forefront of thermal-hydraulic analysis for LWRs including test results from several large-scale facilities. We expect that the contents can offer a guideline to improve reactor thermal-hydraulic analysis codes in future. (author)

  19. Comparative study of Thermal Hydraulic Analysis Codes for Pressurized Water Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yang Hoon; Jang, Mi Suk; Han, Kee Soo [Nuclear Engineering Service and Solution Co. Ltd., Daejeon (Korea, Republic of)

    2015-05-15

    Various codes are used for the thermal hydraulic analysis of nuclear reactors. The use of some codes among these is limited by user and some codes are not even open to general person. Thus, the use of alternative code is considered for some analysis. In this study, simple thermal hydraulic behaviors are analyzed using three codes to show that alternative codes are possible for the analysis of nuclear reactors. We established three models of the simple u-tube manometer using three different codes. RELAP5 (Reactor Excursion and Leak Analysis Program), SPACE (Safety and Performance Analysis CodE for nuclear power Plants), GOTHIC (Generation of Thermal Hydraulic Information for Containments) are selected for this analysis. RELAP5 is widely used codes for the analysis of system behavior of PWRs. SPACE has been developed based on RELAP5 for the analysis of system behavior of PWRs and licensing of the code is in progress. And GOTHIC code also has been widely used for the analysis of thermal hydraulic behavior in the containment system. The internal behavior of u-tube manometer was analyzed by RELAP5, SPACE and GOTHIC codes. The general transient behavior was similar among 3 codes. However, the stabilized status of the transient period analyzed by REPAP5 was different from the other codes. It would be resulted from the different physical models used in the other codes, which is specialized for the multi-phase thermal hydraulic behavior analysis.

  20. CCP Sensitivity Analysis by Variation of Thermal-Hydraulic Parameters of Wolsong-3, 4

    Energy Technology Data Exchange (ETDEWEB)

    You, Sung Chang [KHNP, Daejeon (Korea, Republic of)

    2016-10-15

    The PHWRs are tendency that ROPT(Regional Overpower Protection Trip) setpoint is decreased with reduction of CCP(Critical Channel Power) due to aging effects. For this reason, Wolsong unit 3 and 4 has been operated less than 100% power due to the result of ROPT setpoint evaluation. Typically CCP for ROPT evaluation is derived at 100% PHTS(Primary Heat Transport System) boundary conditions - inlet header temperature, header to header different pressure and outlet header pressure. Therefore boundary conditions at 100% power were estimated to calculate the thermal-hydraulic model at 100% power condition. Actually thermal-hydraulic boundary condition data for Wolsong-3 and 4 cannot be taken at 100% power condition at aged reactor condition. Therefore, to create a single-phase thermal-hydraulic model with 80% data, the validity of the model was confirmed at 93.8%(W3), 94.2%(W4, in the two-phase). And thermal-hydraulic boundary conditions at 100% power were calculated to use this model. For this reason, the sensitivities by varying thermal-hydraulic parameters for CCP calculation were evaluated for Wolsong unit 3 and 4. For confirming the uncertainties by variation PHTS model, sensitivity calculations were performed by varying of pressure tube roughness, orifice degradation factor and SG fouling factor, etc. In conclusion, sensitivity calculation results were very similar and the linearity was constant.

  1. Thermal-Hydraulic Analysis Tasks for ANAV NPPs in Support of Plant Operation and Control

    Directory of Open Access Journals (Sweden)

    L. Batet

    2007-11-01

    Full Text Available Thermal-hydraulic analysis tasks aimed at supporting plant operation and control of nuclear power plants are an important issue for the Asociación Nuclear Ascó-Vandellòs (ANAV. ANAV is the consortium that runs the Ascó power plants (2 units and the Vandellòs-II power plant. The reactors are Westinghouse-design, 3-loop PWRs with an approximate electrical power of 1000 MW. The Technical University of Catalonia (UPC thermal-hydraulic analysis team has jointly worked together with ANAV engineers at different levels in the analysis and improvement of these reactors. This article is an illustration of the usefulness of computational analysis for operational support. The contents presented were operational between 1985 and 2001 and subsequently changed slightly following various organizational adjustments. The paper has two different parts. In the first part, it describes the specific aspects of thermal-hydraulic analysis tasks related to operation and control and, in the second part, it briefly presents the results of three examples of analyses that were performed. All the presented examples are related to actual situations in which the scenarios were studied by analysts using thermal-hydraulic codes and prepared nodalizations. The paper also includes a qualitative evaluation of the benefits obtained by ANAV through thermal-hydraulic analyses aimed at supporting operation and plant control.

  2. European liquid metal thermal-hydraulics R and D: present and future

    International Nuclear Information System (INIS)

    Roelofs, F.; Batta, A.; Bandini, G.; Van Tichelen, K.; Gerschenfeld, A.; Cheng, X.

    2014-01-01

    A large role is attributed in the future within the European Sustainable Nuclear Energy Technology Platform (SNE-TP) and especially the underlying European Sustainable Nuclear Industry Initiative (ESNII) to the application of fast reactors for sustainable nuclear energy production. Specifically, fast reactors are considered attractive because of their possibility to use natural resources efficiently and to reduce the volume and lifetime of nuclear waste. Currently four demonstration projects have a promising outlook in Europe, i.e. the ASTRID project in France, the MYRRHA project in Belgium, the ALFRED project developed in Europe and to be built in Romania, and the ELECTRA project in Sweden. Sodium and lead(-alloys) are envisaged as coolants for these reactors. Obviously, in the development of these reactors, thermal-hydraulics is recognized as a key challenge with emphasis on safety issues. This paper will discuss the present development status of liquid metal cooled reactor thermal-hydraulics as an outcome of the European 7. framework programme THINS (Thermal-Hydraulics for Innovative Nuclear Systems) project. The main project results with respect to liquid metal cooled reactors will be summarized, i.e. turbulence heat transfer model development, fuel assembly analysis, pool thermal-hydraulics, system behaviour, multi-phase physics, and multiscale thermal-hydraulics simulation. In conclusion, the main challenges for future developments will be indicated. Emphasis will be put on the important experimental and numerical challenges. (authors)

  3. End-of-life decision-making in Canada: the report by the Royal Society of Canada expert panel on end-of-life decision-making.

    Science.gov (United States)

    Schüklenk, Udo; van Delden, Johannes J M; Downie, Jocelyn; McLean, Sheila A M; Upshur, Ross; Weinstock, Daniel

    2011-11-01

    This report on end-of-life decision-making in Canada was produced by an international expert panel and commissioned by the Royal Society of Canada. It consists of five chapters. Chapter 1 reviews what is known about end-of-life care and opinions about assisted dying in Canada. Chapter 2 reviews the legal status quo in Canada with regard to various forms of assisted death. Chapter 3 reviews ethical issues pertaining to assisted death. The analysis is grounded in core values central to Canada's constitutional order. Chapter 4 reviews the experiences had in a number of jurisdictions that have decriminalized or recently reviewed assisted dying in some shape or form. Chapter 5 provides recommendations with regard to the provision of palliative care in Canada, as well as recommendations for reform with respect to the various forms of assisted death covered in this document. © 2011 Blackwell Publishing Ltd.

  4. 76 FR 35221 - Proposed Collection; Comment Request; NINR End-of-Life and Palliative Care Science Needs...

    Science.gov (United States)

    2011-06-16

    ... Request; NINR End-of-Life and Palliative Care Science Needs Assessment: Funding Source Questionnaire... Collection: Title: NINR End-of-Life and Palliative Care Science Needs Assessment: Funding Source... Collection: The NINR End-of-Life Science Palliative Care (EOL PC) Needs Assessment: Funding Source...

  5. 76 FR 59145 - Submission for OMB Review; Comment Request; NINR End-of-Life and Palliative Care Science Needs...

    Science.gov (United States)

    2011-09-23

    ...; Comment Request; NINR End-of-Life and Palliative Care Science Needs Assessment: Funding Source (Survey of... End-of-Life and Palliative Care Science Needs Assessment: Funding Source (Survey of Authors). Type of Information Collection Request: NEW. Need and Use of Information Collection: The NINR End-of-Life Science...

  6. End of life care and decision making: Opinions and experiences of the general public, bereaved relatives, and professionals

    NARCIS (Netherlands)

    N.J.H. Raijmakers (Natasja)

    2013-01-01

    textabstractEnd-of-life care aims to improve quality of life of patients and their relatives facing problems associated with life-threatening illness in the last days of life. End-of-life decision-making is an important aspect of end-of-life care that can have a significant impact on the process of

  7. Communication and Decision-Making About End-of-Life Care in the Intensive Care Unit.

    Science.gov (United States)

    Brooks, Laura Anne; Manias, Elizabeth; Nicholson, Patricia

    2017-07-01

    Clinicians in the intensive care unit commonly face decisions involving withholding or withdrawing life-sustaining therapy, which present many clinical and ethical challenges. Communication and shared decision-making are key aspects relating to the transition from active treatment to end-of-life care. To explore the experiences and perspectives of nurses and physicians when initiating end-of-life care in the intensive care unit. The study was conducted in a 24-bed intensive care unit in Melbourne, Australia. An interpretative, qualitative inquiry was used, with focus groups as the data collection method. Intensive care nurses and physicians were recruited to participate in a discipline-specific focus group. Focus group discussions were audio-recorded, transcribed, and subjected to thematic data analysis. Five focus groups were conducted; 17 nurses and 11 physicians participated. The key aspects discussed included communication and shared decision-making. Themes related to communication included the timing of end-of-life care discussions and conducting difficult conversations. Implementation and multidisciplinary acceptance of end-of-life care plans and collaborative decisions involving patients and families were themes related to shared decision-making. Effective communication and decision-making practices regarding initiating end-of-life care in the intensive care unit are important. Multidisciplinary implementation and acceptance of end-of-life care plans in the intensive care unit need improvement. Clear organizational processes that support the introduction of nurse and physician end-of-life care leaders are essential to optimize outcomes for patients, family members, and clinicians. ©2017 American Association of Critical-Care Nurses.

  8. [End-of-life in specialized medical pediatrics department: A French national survey].

    Science.gov (United States)

    Ravanello, Alice; Desguerre, Isabelle; Frache, Sandra; Hubert, Philippe; Orbach, Daniel; Aubry, Régis

    2017-03-01

    In France, most of children die in the hospital. This national survey aimed to achieve better understanding of end-of life care in specialized medical pediatrics departments for children facing the end-of-life, identify the available resources, put forward the difficulties encountered by professionals and describe end-of-life paths of children who died in these departments. This study is based on a nationwide survey conducted among all existing specialized medical pediatrics departments (onco-haematology, neurology, reanimation) in France in 2015. Among 94 specialized medical pediatrics departments in France, 53 participated in our survey (response rate=56%). At the time of the survey, 13% of inpatients were facing the end-of-life. Regarding training, 13% of departments did not have personnel trained in palliative care and 21% did not set up any professional support. However, when taking care of a child's end of life in 2014, 77% of these departments solicited a regional resource team of pediatric palliative care. This survey helps describe 225 end-of-life paths of children decease of a terminal illness in the specialized pediatrics departments. Seventy-two percent suffered from refractory symptoms before their death, 64% were concerned by a terminal sedation and 75% by a limitation of life-sustaining treatment decision. End-of-life care is a reality for specialized pediatrics departments. The frequency of major and refractory symptoms often requires the completion of sedation. The resources of service are acceptable but some deficiencies have been noted especially concerning training and support for caregivers, adaptation of premises or family support. Copyright © 2017. Published by Elsevier SAS.

  9. Current debates on end-of-life sedation: an international expert elicitation study.

    Science.gov (United States)

    Papavasiliou, Evangelia Evie; Payne, Sheila; Brearley, Sarah

    2014-08-01

    End-of-life sedation, though increasingly prevalent and widespread internationally, remains one of the most highly debated medical practices in the context of palliative medicine. This qualitative study aims to elicit and record the perspectives of leading international palliative care experts on current debates. Twenty-one professionals from diverse backgrounds, sharing field-specific knowledge/expertise defined by significant scholarly contribution on end-of-life sedation, were recruited. Open-ended, semi-structured interviews, following a topic-oriented structure reflecting on current debates, were conducted. Results were analysed using thematic content analysis. Three main aspects of sedation were identified and discussed as potentially problematic: (a) continuous deep sedation as an extreme facet of end-of-life sedation, (b) psycho-existential suffering as an ambivalent indication for sedation and (c) withdrawal or withholding of artificial nutrition and hydration as potentially life-shortening. On these grounds, concerns were reported over end-of-life sedation being morally equivalent to euthanasia. Considerable emphasis was placed on intentions as the distinguishing factor between end-of-life acts, and protective safeguards were introduced to distance sedation from euthanasia. This study shows that, despite the safeguards introduced, certain aspects of sedation, including the intentions associated with the practice, are still under question, parallels being drawn between end-of-life sedation and euthanasia. This reaffirms the existence of a grey area surrounding the two practices, already evidenced in countries where euthanasia is legalized. More clarity over the issues that generate this grey area, with their causes being uncovered and eliminated, is imperative to resolve current debates and effectively inform research, policy and practice of end-of-life sedation.

  10. Sustainable Logistics of End-of-life Vehicles – Trends in Europe

    Directory of Open Access Journals (Sweden)

    Agata Mesjasz-Lech

    2017-06-01

    Full Text Available Purpose of the article: In the article we have focused on the trends determining the development of reverse logistics of end-of-life vehicles in selected European countries. The analysis concentrates on quantity of end-of-life vehicles which are especially interesting for reverse logistics because of their fitness for recovery or reuse. End-of-life products contain fully valuable elements which, according to the idea of sustainable use of resources, should be recovered. Accordingly, reverse logistics aims at protecting natural resources and the environment through reintroduction of processed waste materials into the economic cycle as valuable products and materials. Methodology/methods: The aim of the article was achieved on the basis of a critical analysis of subject literature and the analysis of statistical data. In the article the method of descriptive and mathematical statistics and dynamic analysis were used. The 2006–2014 years were analyzed. The data come from the data base of the Eurostat, the statistical office of the European Union. The following variables were taken into account: the amount of end-of-life vehicles (in tonnes and in number of cars, reuse level (in tonnes, recovery level (in tonnes, and recycling level (in tonnes. The analysis was based on a t-Student test for two average values of dependent samples, sign test and the Wilcoxon signed rank test. In order to see if the reverse logistics actions implemented in European countries were effective, the analysis compares the average values of individual variables from the year 2014 and 2006. Measurements were done for the same countries on the same element of population. The chain indexes and the average change tempo for specified variables were calculated. The similarity of the formation of specified variables in each year was compared on the basis of the index of similarity structures. Scientific aim: The scientific aim of the article is to identify the basic trends

  11. Test results of the new NSSS thermal-hydraulics program of the KNPEC-2 simulator

    International Nuclear Information System (INIS)

    Jeong, J. Z.; Kim, K. D.; Lee, M. S.; Hong, J. H.; Lee, Y. K.; Seo, J. S.; Kweon, K. J.; Lee, S. W.

    2001-01-01

    As a part of the KNPEC-2 Simulator Upgrade Project, KEPRI and KAERI have developed a new NSSS thermal-hydraulics program, which is based on the best-estimate system code, RETRAN. The RETRAN code was originally developed for realistic simulation of thermal-hydraulic transient in power plant systems. The capability of 'real-time simulation' and robustness' should be first developed before being implemented in full-scope simulators. For this purpose, we have modified the RETRAN code by (i) eliminating the correlations' discontinuities between flow regime maps, (ii) simplifying physical correlations, (iii) correcting errors in the original program, and (iv) others. This paper briefly presents the test results fo the new NSSS thermal-hydraulics program

  12. Thermal hydraulic considerations in liquid-metal-cooled components of tokamak fusion reactors

    International Nuclear Information System (INIS)

    Picologlou, B.F.; Reed, C.B.; Hua, T.Q.

    1989-01-01

    The basic considerations of MHD thermal hydraulics for liquid-metal-cooled blankets and first walls of tokamak fusion reactors are discussed. The liquid-metal MHD program of Argonne National Laboratory (ANL) dedicated to analytical and experimental investigations of reactor relevant MHD flows and development of relevant thermal hydraulic design tools is presented. The status of the experimental program and examples of local velocity measurements are given. An account of the MHD codes developed to date at ANL is also presented as is an example of a 3-D thermal hydraulic analysis carried out with such codes. Finally, near term plans for experimental investigations and code development are outlined. 20 refs., 8 figs., 1 tab

  13. 11. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-11)

    International Nuclear Information System (INIS)

    Lemonnier, H.

    2005-01-01

    The main topics covered by the NURETH 11 meeting are the thermal-hydraulics of existing and future nuclear power plants as foreseen by the Generation IV worldwide initiative. Normal operation and accidental situations are also relevant topics of the Conference. The topics cover modeling, experiments, instrumentation and numerical simulations related to flow and heat transfer in nuclear reactors with a special emphasis on the advances of multiphase CFD methods. The first part of this Book of Abstracts enumerates the Organizing Scientific Societies, the Sponsors of the Conference, the Conference Chairs, and the members of the Steering Committee and of the Technical Program Committee. The second part of this Book of Abstracts contains the list of the titles of the contributed papers. Each item includes the log number of the paper, the abstract of which can therefore be easily located in the next section of this book. The titles of the papers have been sorted out by topics to provide a synthetic view of the contributions in a selected domain. The last section of this Book includes an index of authors and co-authors with a reference to the log number(s) of their contributed paper(s). Finally, the CD-Rom of the Conference Proceedings containing the full-length papers is inserted at the inside back cover. Sessions content: A - two-phase flow and heat transfer fundamentals: computational and mathematical techniques (numerical schemes, LBM, BEM, mesh-less, etc.); contact angle and wettability phenomena; experiments and data bases for the assessment and the verification of 3D models; flow regime identification and modelling; heat transfer near critical pressure and supercritical water reactors; interfacial area (data base, modeling, measurement techniques); instrumentation techniques; micro-scale basic phenomena, fluid flow and heat transfer; scaling methods; counter current flow; B - code developments: containment analysis; core thermal-hydraulics and subchannel analysis

  14. Parametric study on thermal-hydraulic characteristics of high conversion light water reactor

    International Nuclear Information System (INIS)

    Mori, Takamasa; Nakagawa, Masayuki; Fujii, Sadao.

    1988-11-01

    To assess the feasibility of high conversion light water reactors (HCLWRs) from the thermal-hydraulic viewpoint, parametric study on thermal-hydraulic characteristics of HCLWR has been carried out by using a unit cell model. It is assumed that a HCLWR core is contained in a current 1000 MWe PWR plant. At the present study, reactor core parameters such as fuel pin diameter, pitch, core height and linear heat rate are widely and parametrically changed to survey the relation between these parameters and the basic thermal-hydraulic characteristics, i.e. maximum fuel temperature, minimum DNBR, reduction of reactor thermal output and so on. The validity of the unit cell model used has been ensured by comparison with the result of a subchannel analysis carried out for a whole core. (author)

  15. Full vessel CFD analysis on thermal-hydraulic characteristics of CPR1000 PWR

    International Nuclear Information System (INIS)

    Chao Yanmeng; Yang Lixin; Zhang Mingqian

    2014-01-01

    To obtain flow distributions and thermal-hydraulic properties in a full vessel PWR under limited computation ability and time, a full vessel simulation model of CPR1000 was built based on two simplification methods. One simplified the inner geometry of the control rod guide tubes using equivalent flow area. Another substituted the core by a porous domain to maintain the pressure drop and temperature rise. After the computation, global and localized flow distributions, hydraulic loads of some main assemblies were obtained, as well as other thermal-hydraulic properties. The results indicate the flow distribution in the full vessel is asymmetrical. Therefore it is essential to use the full vessel model to simulate. The calculated thermal-hydraulic characteristics agree well with the operation statistics, providing the reference data for the reactor safety operation. (authors)

  16. Visualization and measurement by image processing of thermal hydraulic phenomena by neutron radiography

    International Nuclear Information System (INIS)

    Takenaka, Nobuyuki

    1996-01-01

    Neutron Radiography was applied to visualization of thermal hydraulic phenomena and measurement was carried out by image processing the visualized images. Since attenuation of thermal neutron rays is high in ordinary liquids like water and organic fluid while it is low in most of metals, liquid flow behaviors can be visualized through a metallic wall by neutron radiography. Measurement of void fraction and flow vector field which is important to study thermal hydraulic phenomena can be carried out by image processing the images obtained by the visualization. Various two-phase and liquid metal flows were visualized by a JRR-3M thermal neutron radiography system in the present study. Multi-dimensional void fraction distributions in two-phase flows and flow vector fields in liquid metals, which are difficult to measure by the other methods, were successfully measured by image processing. It was shown that neutron radiography was efficiently applicable to study thermal hydraulic phenomena. (author)

  17. Thermal-hydraulics of the Loviisa reactor pressure vessel overcooling transients

    International Nuclear Information System (INIS)

    Tuomisto, Harri.

    1987-06-01

    In the Loviisa reactor pressure vessel safety analyses, the thermal-hydraulics of various overcooling transients has been evaluated to give pertinent initial data for fracture-mechanics calculations. The thermal-hydraulic simulations of the developed overcooling scenarios have been performed using best-estimate thermal-hydraulic computer codes. Experimental programs have been carried out to study phenomena related to natural circulation interruptions in the reactor coolant system. These experiments include buoyancy-induced phenomena such as thermal mixing and stratification of cold high-pressure safety injection water in the cold legs and the downcomer, and oscillations of the single-phase natural circulation. In the probabilistic pressurized thermal shock study, the Loviisa training simulator and the advanced system code RELAP5/MOD2 were utilized to simulate selected sequences. Flow stagnation cases were separately calculated with the REMIX computer program. The methods employed were assessed for these calculations against the plant data and own experiments

  18. Thermal-hydraulic analysis of PWR small assembly for irradiation test of CARR

    International Nuclear Information System (INIS)

    Yin Hao; Zou Yao; Liu Xingmin

    2015-01-01

    The thermal-hydraulic behaviors of the PWR 4 × 4 small assembly tested in the high temperature and high pressure loop of China Advanced Research Reactor were analyzed. The CFD method was used to carry out 3D simulation of the model, thus detailed thermal-hydraulic parameters were obtained. Firstly, the simplified model was simulated to give the 3D temperature and velocity distributions and analyze the heat transfer process. Then the whole scale small assembly model was simulated and the simulation results were compared with those of simplified rod bundle model. Its flow behavior was studied and flow mixing characteristics of the grids were analyzed, and the mixing factor of the grid was calculated and can be used for further thermal-hydraulic study. It is shown that the highest temperature of the fuel rod meets the design limit and the mixing effect of the grid is obvious. (authors)

  19. Physician Communication in Pediatric End-of-Life Care: A Simulation Study.

    Science.gov (United States)

    Bateman, Lori Brand; Tofil, Nancy M; White, Marjorie Lee; Dure, Leon S; Clair, Jeffrey Michael; Needham, Belinda L

    2016-12-01

    The objective of this exploratory study is to describe communication between physicians and the actor parent of a standardized 8-year-old patient in respiratory distress who was nearing the end of life. Thirteen pediatric emergency medicine and pediatric critical care fellows and attendings participated in a high-fidelity simulation to assess physician communication with an actor-parent. Fifteen percent of the participants decided not to initiate life-sustaining technology (intubation), and 23% of participants offered alternatives to life-sustaining care, such as comfort measures. Although 92% of the participants initiated an end-of-life conversation, the quality of that discussion varied widely. Findings indicate that effective physician-parent communication may not consistently occur in cases involving the treatment of pediatric patients at the end of life in emergency and critical care units. The findings in this study, particularly that physician-parent end-of-life communication is often unclear and that alternatives to life-sustaining technology are often not offered, suggest that physicians need more training in both communication and end-of-life care. © The Author(s) 2015.

  20. Assessment and Treatment Considerations for Post Traumatic Stress Disorder at End of Life.

    Science.gov (United States)

    Glick, Debra M; Cook, Joan M; Moye, Jennifer; Kaiser, Anica Pless

    2018-01-01

    Post traumatic stress disorder (PTSD) may first emerge, reemerge, or worsen as individuals approach end of life and may complicate the dying process. Unfortunately, lack of awareness of the occurrence and/or manifestation of PTSD at end of life can lead to PTSD going unaddressed. Even if PTSD is properly diagnosed, traditional evidence-based trauma-focused treatments may not be feasible or advisable with this group as many patients at end of life often lack the physical and mental stamina to participate in traditional psychotherapy. This article reviews the clinical and empirical literature on PTSD at end of life, as well as discusses assessment and psychotherapy treatment issues with this neglected population. In addition, it expands on the current reviews of this literature 1-3 by extrapolating results from nontraditional treatment approaches with other patient populations. Elements of these approaches with patients sharing similar characteristics and/or comorbidities with patients with PTSD at end of life may provide additional benefits for the latter population. Clinical implications and suggestions for interdisciplinary care providers are provided.

  1. The Evolution of End-of-Life Care: Ethical Implications for Case Management.

    Science.gov (United States)

    Fink-Samnick, Ellen

    2016-01-01

    This article: : Applicable to all health care sectors where case management is practiced. Few topics are more intimate and multifaceted for case managers than engaging with today's culturally diverse patient populations around end-of-life processes. The already prominent focus of this issue has been further elevated by a series of events to receive public attention. These include the Institute of Medicine's 2014 report-Dying in America: Improving Quality and Honoring Individual Preferences Near the End of Life, rising numbers of patients around the globe requesting to end life on their own terms, and corresponding death with dignity initiatives and legislation.Another vital factor in the end-of-life equation involves how the latest generation of shared decision making influences the management of treatment dialogues among practitioners, patients, as well as insurance companies. Case managers are at the intersection of these complex interactions, working to achieve ethical, as well as legal accountability to the patient, employer, and profession while balancing personal perspectives. Professionals strive to effectively intervene with patients and their support systems facing end-of-life care decisions. It is essential case managers actively consider the intricacies of ethical practice and current contexts including death with dignity legislation, shared decision making, and shifts in regulations and reimbursement for end-of-life care.Case management's ethical envelope will continue to be pushed. To that end amid shifting societal constructs, professionals must have mastery of applicable codes, standards, principles, and rules essential for adherence to ethical practice.

  2. Neutronics - thermal-hydraulics coupling: application to the helium-cooled fast reactor

    International Nuclear Information System (INIS)

    Vaiana, F.

    2009-11-01

    This thesis focuses on the study of interactions between neutron-kinetics and thermal-hydraulics. Neutron-kinetics allow to calculate the power in a nuclear reactor and the temperature evolution of materials where this power is deposited is known thanks to thermal-hydraulics. Moreover, when the temperatures evolve, the densities and cross sections change. These two disciplines are thus coupled. The first part of this work corresponds to the study and development of a method which allows to simulate transients in nuclear reactors and especially with a Monte-Carlo code for neutron-kinetics. An algorithm for the resolution of the neutron transport equation has been established and validated with a benchmark. In thermal-hydraulics, a porous media approach, based on another thesis, is considered. This gives the opportunity to solve the equations on the whole core without unconscionable computation time. Finally, a theoretical study has been performed on the statistical uncertainties which result from the use of a Monte-Carlo code and which spread from the reactivity to the power and from the power to the temperatures. The second part deals with the study of a misplaced control rod withdrawing in a GFR (helium-cooled fast reactor), a fourth generation reactor. Some models allowing to calculate neutron-kinetics and thermal-hydraulics in the core (which contains assemblies built up with fuel plates) were defined. In thermal-hydraulics, a model for the core based on the porous media approach and a fuel plate homogenization model have been set up. A similar homogenization model has been studied for neutron-kinetics. Finally, the control rod withdrawing transient where we can observe the power raising and the stabilisation by thermal feedback has been performed with the Monte-Carlo code Tripoli for neutron-kinetics and the code Trio-U for thermal-hydraulics. (author)

  3. European activities on crosscutting thermal-hydraulic phenomena for innovative nuclear systems

    Energy Technology Data Exchange (ETDEWEB)

    Cheng, X., E-mail: xu.cheng@kit.edu [Karlsruhe Institute of Technology (KIT) (Germany); Batta, A. [Karlsruhe Institute of Technology (KIT) (Germany); Bandini, G. [Italian National Agency for New Technologies, Energy and Sustainable Economic Development (ENEA) (Italy); Roelofs, F. [Nuclear Research and Consultancy Group (NRG) (Netherlands); Van Tichelen, K. [Studiecentrum voor Kernenergie – Centre d’étude de l’Energie Nucléaire (SCK-CEN) (Belgium); Gerschenfeld, A. [Commissariat à l’Energie Atomique (CEA) (France); Prasser, M. [Paul Scherrer Institute (PSI) (Switzerland); Papukchiev, A. [Gesellschaft für Anlagen- und Reaktorsicherheit mbH (GRS) (Germany); Hampel, U. [Helmholtz-Zentrum Dresden-Rossendorf e.V. (HZDR) (Germany); Ma, W.M. [Kungliga Tekniska Högskolan (KTH) (Sweden)

    2015-08-15

    Highlights: • This paper serves as a guidance of the special issue. • The technical tasks and methodologies applied to achieve the objectives have been described. • Main results achieved so far are summarized. - Abstract: Thermal-hydraulics is recognized as a key scientific subject in the development of innovative reactor systems. In Europe, a consortium is established consisting of 24 institutions of universities, research centers and nuclear industries with the main objectives to identify and to perform research activities on important crosscutting thermal-hydraulic issues encountered in various innovative nuclear systems. For this purpose the large-scale integrated research project THINS (Thermal-Hydraulics of Innovative Nuclear Systems) is launched in the 7th Framework Programme FP7 of European Union. The main topics considered in the THINS project are (a) advanced reactor core thermal-hydraulics, (b) single phase mixed convection, (c) single phase turbulence, (d) multiphase flow, and (e) numerical code coupling and qualification. The main objectives of the project are: • Generation of a data base for the development and validation of new models and codes describing the selected crosscutting thermal-hydraulic phenomena. • Development of new physical models and modeling approaches for more accurate description of the crosscutting thermal-hydraulic phenomena. • Improvement of the numerical engineering tools for the design analysis of the innovative nuclear systems. This paper describes the technical tasks and methodologies applied to achieve the objectives. Main results achieved so far are summarized. This paper serves also as a guidance of this special issue.

  4. Thermal hydraulic issues and challenges for current and new generation FBRs

    Energy Technology Data Exchange (ETDEWEB)

    Chellapandi, P.; Velusamy, K., E-mail: kvelu@igcar.gov.in

    2015-12-01

    Highlights: • We present challenges in thermal hydraulic design of sodium cooled fast reactors. • We present roadmap of Indian fast reactor program and innovative design concepts. • Analysis methodology for thermal striping and thermal stratification are highlighted. • Design solutions for gas entrainment are presented. • Experimental approaches for normal and post accident decay heat removal are highlighted. - Abstract: Pool type sodium cooled fast reactors pose several design challenges and among them, certain thermal hydraulics and structural mechanics issues are special. High frequency temperature fluctuations due to thermal striping, thermal stratifications and sodium free level fluctuations at the liquid–cover gas interfaces are to be investigated carefully to eliminate high cycle thermal fatigue of structures. Solutions to address the core thermal hydraulics call for high power computing. Innovative concepts and methods are developed to carry out plant dynamics and safety studies. Particularly, extensive numerical and experimental simulation techniques are needed for understanding and solving the gas entrainment mechanisms and its effects on core safety. Though decay heat removal through natural convection is achievable in a pool type SFR, demonstration of design solutions conceived in the reactor and performance of diverse systems under all operating conditions, especially over prolonged station blackout situations needs advanced CFD computations and should be validated by relatively large scale simulated experiments. These issues are addressed in this paper under five broad topics: special thermal hydraulic issues to be addressed in SFR, thermal hydraulic design and analysis, plant dynamics studies, safety studies and evolving thermal hydraulic studies for the future FBRs. The 500 MWe Prototype Fast Breeder Reactor (PFBR) is taken as the reference design for addressing the issues. Indian fast reactor programme is highlighted in the introduction

  5. Thermal hydraulic test of advanced fuel bundle with spectral shift rod (SSR) for BWR. Effect of thermal hydraulic parameters on steady state characteristics

    International Nuclear Information System (INIS)

    Kondo, Takao; Kitou, Kazuaki; Chaki, Masao; Ohga, Yukiharu; Makigami, Takeshi

    2011-01-01

    Japanese national project of next generation light water reactor (LWR) development started in 2008. Under this project, spectral shift rod (SSR) is being developed. SSR, which replaces conventional water rod (WR) of boiling water reactor (BWR) fuel bundle, was invented to enhance the BWR's merit, spectral shift effect for uranium saving. In SSR, water boils by neutron and gamma-ray direct heating and water level is formed as a boundary of the upper steam region and the lower water region. This SSR water level can be controlled by core flow rate, which amplifies the change of average core void fraction, resulting in the amplified spectral shift effect. This paper presents the steady state test results of the base geometry case in SSR thermal hydraulic test, which was conducted under the national project of next generation LWR. In the test, thermal hydraulic parameters, such as flow rate, pressure, inlet subcooling and heater rod power are changed to evaluate these effects on SSR water level and other SSR characteristics. In the test results, SSR water level rose as flow rate rose, which showed controllability of SSR water level by flow rate. The sensitivities of other thermal hydraulic parameters on SSR water level were also evaluated. The obtained data of parameter's sensitivities is various enough for the further analytical evaluation. The fluctuation of SSR water level was also measured to be small enough. As a result, it was confirmed that SSR's steady state performance was as planned and that SSR design concept is feasible. (author)

  6. Simulation of Thermal-hydraulic Process in Reactor of HTR-PM

    International Nuclear Information System (INIS)

    Zhou Kefeng; Zhou Yangping; Sui Zhe; Ma Yuanle

    2014-01-01

    This paper provides the physical process in the reactor of High Temperature Gas-cooled Reactor Pebble-bed Module (HTR-PM) and introduces the standard operation conditions. The FORTRAN code developed for the thermal hydraulic module of Full-Scale Simulator (FSS) of HTR-PM is used to simulate two typical operation transients including cold startup process and cold shutdown process. And the results were compared to the safety analysis code, namely TINTE. The good agreement indicates that the code is applicable for simulating the thermal-hydraulic process in reactor of HTR-PM. And for long time transient process, the code shows good stability and convergence. (author)

  7. TRAC-B thermal-hydraulic analysis of the Black Fox boiling water reactor

    International Nuclear Information System (INIS)

    Martin, R.P.

    1993-05-01

    Thermal-hydraulic analyses of six hypothetical accident scenarios for the General Electric Black Fox Nuclear Project boiling water reactor were performed using the TRAC-BF1 computer code. This work is sponsored by the US Nuclear Regulatory Commission and is being done in conjunction with future analysis work at the US Nuclear Regulatory Commission Technical Training Center in Chattanooga, Tennessee. These accident scenarios were chosen to assess and benchmark the thermal-hydraulic capabilities of the Black Fox Nuclear Project simulator at the Technical Training Center to model abnormal transient conditions

  8. Light-water-reactor coupled neutronic and thermal-hydraulic codes

    International Nuclear Information System (INIS)

    Diamond, D.J.

    1982-01-01

    An overview is presented of computer codes that model light water reactor cores with coupled neutronics and thermal-hydraulics. This includes codes for transient analysis and codes for steady state analysis which include fuel depletion and fission product buildup. Applications in nuclear design, reactor operations and safety analysis are given and the major codes in use in the USA are identified. The neutronic and thermal-hydraulic methodologies and other code features are outlined for three steady state codes (PDQ7, NODE-P/B and SIMULATE) and four dynamic codes (BNL-TWIGL, MEKIN, RAMONA-3B, RETRAN-02). Speculation as to future trends with such codes is also presented

  9. Current and anticipated uses of thermal hydraulic codes at the Japan Atomic Energy Research Institute

    Energy Technology Data Exchange (ETDEWEB)

    Akimoto, Hajime; Kukita; Ohnuki, Akira [Japan Atomic Energy Research Institute, Ibaraki (Japan)

    1997-07-01

    The Japan Atomic Energy Research Institute (JAERI) is conducting several research programs related to thermal-hydraulic and neutronic behavior of light water reactors (LWRs). These include LWR safety research projects, which are conducted in accordance with the Nuclear Safety Commission`s research plan, and reactor engineering projects for the development of innovative reactor designs or core/fuel designs. Thermal-hydraulic and neutronic codes are used for various purposes including experimental analysis, nuclear power plant (NPP) safety analysis, and design assessment.

  10. CHF predictor derived from a 3D thermal-hydraulic code and an advanced statistical method

    International Nuclear Information System (INIS)

    Banner, D.; Aubry, S.

    2004-01-01

    A rod bundle CHF predictor has been determined by using a 3D code (THYC) to compute local thermal-hydraulic conditions at the boiling crisis location. These local parameters have been correlated to the critical heat flux by using an advanced statistical method based on spline functions. The main characteristics of the predictor are presented in conjunction with a detailed analysis of predictions (P/M ratio) in order to prove that the usual safety methodology can be applied with such a predictor. A thermal-hydraulic design criterion is obtained (1.13) and the predictor is compared with the WRB-1 correlation. (author)

  11. SUPERENERGY-2: a multiassembly, steady-state computer code for LMFBR core thermal-hydraulic analysis

    Energy Technology Data Exchange (ETDEWEB)

    Basehore, K.L.; Todreas, N.E.

    1980-08-01

    Core thermal-hydraulic design and performance analyses for Liquid Metal Fast Breeder Reactors (LMFBRs) require repeated detailed multiassembly calculations to determine radial temperature profiles and subchannel outlet temperatures for various core configurations and subassembly structural analyses. At steady-state, detailed core-wide temperature profiles are required for core restraint calculations and subassembly structural analysis. In addition, sodium outlet temperatures are routinely needed for each reactor operating cycle. The SUPERENERGY-2 thermal-hydraulic code was designed specifically to meet these designer needs. It is applicable only to steady-state, forced-convection flow in LMFBR core geometries.

  12. Comparison for the interfacial and wall friction models in thermal-hydraulic system analysis codes

    International Nuclear Information System (INIS)

    Hwang, Moon Kyu; Park, Jee Won; Chung, Bub Dong; Kim, Soo Hyung; Kim, See Dal

    2007-07-01

    The average equations employed in the current thermal hydraulic analysis codes need to be closed with the appropriate models and correlations to specify the interphase phenomena along with fluid/structure interactions. This includes both thermal and mechanical interactions. Among the closure laws, an interfacial and wall frictions, which are included in the momentum equations, not only affect pressure drops along the fluid flow, but also have great effects for the numerical stability of the codes. In this study, the interfacial and wall frictions are reviewed for the commonly applied thermal-hydraulic system analysis codes, i.e. RELAP5-3D, MARS-3D, TRAC-M, and CATHARE

  13. Thermal - hydraulic analysis of pressurizer water reactors using the model of open lateral boundary

    International Nuclear Information System (INIS)

    Borges, R.C.

    1980-10-01

    A computational method is developed for thermal-hydraulic analysis, where the channel may be analysed by more than one independent steps of calculation. This is made possible by the incorporation of the model of open lateral boundary in the code COBRA-IIIP, which permits the determination of the subchannel of an open lattice PWR core in a multi-step calculation. The thermal-hydraulic code COBRA-IIIP, developed at the Massachusetts Institute of Technology, is used as the basic model for this study. (Author) [pt

  14. Thermal-hydraulic analysis of PWR core including intermediate flow mixers with the THYC code

    International Nuclear Information System (INIS)

    Mur, J.; Meignin, J.C.

    1997-07-01

    Departure from nucleate boiling (DNB) is one of the major limiting factors of pressurized water reactors (PWRs). Safety requires that occurrence of DNB should be precluded under normal or incidental operating conditions. The thermal-hydraulic THYC code developed by EDF is described. The code is devoted to heat and mass transfer in nuclear components. Critical Heat Flux (CHF) is predicted from local thermal-hydraulic parameters such as pressure, mass flow rate, and quality. A three stage methodology to evaluate thermal margins in order to perform standard core design is described. (K.A.)

  15. Thermal-hydraulic analysis of PWR core including intermediate flow mixers with the THYC code

    Energy Technology Data Exchange (ETDEWEB)

    Mur, J. [Electricite de France (EDF), 78 - Chatou (France); Meignin, J.C. [Electricite de France (EDF), 69 - Villeurbanne (France)

    1997-07-01

    Departure from nucleate boiling (DNB) is one of the major limiting factors of pressurized water reactors (PWRs). Safety requires that occurrence of DNB should be precluded under normal or incidental operating conditions. The thermal-hydraulic THYC code developed by EDF is described. The code is devoted to heat and mass transfer in nuclear components. Critical Heat Flux (CHF) is predicted from local thermal-hydraulic parameters such as pressure, mass flow rate, and quality. A three stage methodology to evaluate thermal margins in order to perform standard core design is described. (K.A.) 8 refs.

  16. Neutronic and thermal hydraulic analysis for production of fission molybdenum-99 at Pakistan Research Reactor-1

    Energy Technology Data Exchange (ETDEWEB)

    Mushtaq, A. [Isotope Production Division, Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad (Pakistan)], E-mail: mushtaqa@pinstech.org.pk; Iqbal, Massod; Bokhari, Ishtiaq Hussain; Mahmood, Tariq; Mahmood, Tayyab; Ahmad, Zahoor; Zaman, Qamar [Nuclear Engineering Division, Pakistan Institute of Nuclear Science and Technology, P.O. Nilore, Islamabad (Pakistan)

    2008-02-15

    Neutronic and thermal hydraulic analysis for the fission molybdenum-99 production at PARR-1 has been performed. Low enriched uranium foil (<20% {sup 235}U) will be used as target material. Annular target designed by ANL (USA) will be irradiated in PARR-1 for the production of 100 Ci of molybdenum-99 at the end of irradiation, which will be sufficient to prepare required {sup 99}Mo/{sup 99m}Tc generators at PINSTECH and its supply in the country. Neutronic and thermal hydraulic analysis were performed using various codes. Data shows that annular targets can be safely irradiated in PARR-1 for production of required amount of fission molybdenum-99.

  17. Perturbative methods applied for sensitive coefficients calculations in thermal-hydraulic systems

    International Nuclear Information System (INIS)

    Andrade Lima, F.R. de

    1993-01-01

    The differential formalism and the Generalized Perturbation Theory (GPT) are applied to sensitivity analysis of thermal-hydraulics problems related to pressurized water reactor cores. The equations describing the thermal-hydraulic behavior of these reactors cores, used in COBRA-IV-I code, are conveniently written. The importance function related to the response of interest and the sensitivity coefficient of this response with respect to various selected parameters are obtained by using Differential and Generalized Perturbation Theory. The comparison among the results obtained with the application of these perturbative methods and those obtained directly with the model developed in COBRA-IV-I code shows a very good agreement. (author)

  18. SUPERENERGY-2: a multiassembly, steady-state computer code for LMFBR core thermal-hydraulic analysis

    International Nuclear Information System (INIS)

    Basehore, K.L.; Todreas, N.E.

    1980-08-01

    Core thermal-hydraulic design and performance analyses for Liquid Metal Fast Breeder Reactors (LMFBRs) require repeated detailed multiassembly calculations to determine radial temperature profiles and subchannel outlet temperatures for various core configurations and subassembly structural analyses. At steady-state, detailed core-wide temperature profiles are required for core restraint calculations and subassembly structural analysis. In addition, sodium outlet temperatures are routinely needed for each reactor operating cycle. The SUPERENERGY-2 thermal-hydraulic code was designed specifically to meet these designer needs. It is applicable only to steady-state, forced-convection flow in LMFBR core geometries

  19. Condition Assessment and End-of-Life Prediction System for Electric Machines and Their Loads

    Science.gov (United States)

    Parlos, Alexander G.; Toliyat, Hamid A.

    2005-01-01

    An end-of-life prediction system developed for electric machines and their loads could be used in integrated vehicle health monitoring at NASA and in other government agencies. This system will provide on-line, real-time condition assessment and end-of-life prediction of electric machines (e.g., motors, generators) and/or their loads of mechanically coupled machinery (e.g., pumps, fans, compressors, turbines, conveyor belts, magnetic levitation trains, and others). In long-duration space flight, the ability to predict the lifetime of machinery could spell the difference between mission success or failure. Therefore, the system described here may be of inestimable value to the U.S. space program. The system will provide continuous monitoring for on-line condition assessment and end-of-life prediction as opposed to the current off-line diagnoses.

  20. Community gardens as sites of solace and end-of-life support: a literature review.

    Science.gov (United States)

    Marsh, Pauline; Spinaze, Anna

    2016-05-01

    In a pilot project, members of a community garden explored how they might provide better end-of-life support for their regional community. As part of the project, a literature review was undertaken to investigate the nexus between community gardens and end-of-life experiences (including grief and bereavement) in academic research. This article documents the findings of that review. The authors discovered there is little academic material that focuses specifically on community gardens and end-of-life experiences, but nonetheless the two subjects were seen to intersect. The authors found three points of commonality: both share a need and capacity for a) social/informal support, b) therapeutic space, and c) opportunities for solace.

  1. Spirituality in end-of-life care: attending the person on their journey.

    LENUS (Irish Health Repository)

    Hayden, Deborah

    2011-11-01

    Spirituality is a fundamental element to the human experience of health and healing, illness and dying. Spiritual care is an essential component of palliative and end-of-life care provision and is the responsibility of all staff and carers involved in the care of patients and families. As end-of-life care is a significant element of community nursing, this article explores the relevancy of spirituality to end-of-life practice, the challenge of defining spirituality and the attributes and skills required for the practice of spiritual care. The aim of is to encourage self reflection and open dialogue about the subject, thus enhancing community nurses\\' understanding of spiritual care practice. By reflecting and generating talk about the practice of spiritual care, it may become more normalized, recognized, and practically meaningful, thereby retaining its significance in holistic nursing.

  2. End-of-life decisions in Malaysia: Adequacies of ethical codes and developing legal standards.

    Science.gov (United States)

    Kassim, Puteri Nemie Jahn; Alias, Fadhlina

    2015-06-01

    End-of-life decision-making is an area of medical practice in which ethical dilemmas and legal interventions have become increasingly prevalent. Decisions are no longer confined to clinical assessments; rather, they involve wider considerations such as a patient's religious and cultural beliefs, financial constraints, and the wishes and needs of family members. These decisions affect everyone concerned, including members of the community as a whole. Therefore it is imperative that clear ethical codes and legal standards are developed to help guide the medical profession on the best possible course of action for patients. This article considers the relevant ethical, codes and legal provisions in Malaysia governing certain aspects of end-of-life decision-making. It highlights the lack of judicial decisions in this area as well as the limitations with the Malaysian regulatory system. The article recommends the development of comprehensive ethical codes and legal standards to guide end-of-life decision-making in Malaysia.

  3. Reflections on Hope and Its Implications for End-of-Life Care.

    Science.gov (United States)

    Mattes, Malcolm D; Sloane, Michelle A

    2015-05-01

    Physicians caring for individuals with life-altering, incurable illnesses often have a desire to convey a sense of hope while also helping their patients prepare for the end of life to minimize unnecessary suffering and grief. Unfortunately, in the United States, most people receive more-aggressive treatments toward the end of life than studies would suggest that they desire. This reflects the challenging task of balancing optimism and realism, and how providing a false sense of hope for a cure for too long a time while avoiding advance care planning may contribute significantly to the problem. This article explores the interplay of hope and advance care planning, and suggests a need for excellent individualized communication in the setting of advanced cancer to improve end-of-life care. © 2015, Copyright the Authors Journal compilation © 2015, The American Geriatrics Society.

  4. End-of-life care beliefs among Hindu physicians in the United States.

    Science.gov (United States)

    Ramalingam, Vijaya Sivalingam; Saeed, Fahad; Sinnakirouchenan, Ramapriya; Holley, Jean L; Srinivasan, Sinnakirouchenan

    2015-02-01

    Several studies from the United States and Europe showed that physicians' religiosity is associated with their approach to end-of-life care beliefs. No such studies have focused exclusively on Hindu physicians practicing in the United States. A 34-item questionnaire was sent to 293 Hindu physicians in the United States. Most participants believed that their religious beliefs do not influence their practice of medicine and do not interfere with withdrawal of life support. The US practice of discussing end-of-life issues with the patient, rather than primarily with the family, seems to have been adopted by Hindu physicians practicing in the United States. It is likely that the ethical, cultural, and patient-centered environment of US health care has influenced the practice of end-of-life care by Hindu physicians in this country. © The Author(s) 2013.

  5. End-of-life expectations and experiences among nursing home patients and their relatives

    DEFF Research Database (Denmark)

    Fosse, Anette; Schaufel, Margrethe Aase; Ruths, Sabine

    2014-01-01

    . CONCLUSION: Nursing home patients and their relatives wanted doctors more involved in end-of-life care. They expected doctors to acknowledge their preferences and provide guidance and symptom relief. PRACTICE IMPLICATIONS: High-quality end-of-life care in nursing homes relies on organization, funding......OBJECTIVE: Synthesize research about patients' and relatives' expectations and experiences on how doctors can improve end-of-life care in nursing homes. METHODS: We systematically searched qualitative studies in English in seven databases (Medline, Embase, PsycINFO, CINAHL, Ageline, Cochrane...... decision-makers reported uncertainty and distress when guidance from health personnel was lacking. They worried about staff shortage and emphasized doctor availability. Relatives and health personnel seldom recognized patients' ability to consent, and patients' preferences were not always recognized...

  6. Economic impact analysis of an end-of-life programme for nursing home residents.

    Science.gov (United States)

    Teo, W-S Kelvin; Raj, Anusha Govinda; Tan, Woan Shin; Ng, Charis Wei Ling; Heng, Bee Hoon; Leong, Ian Yi-Onn

    2014-05-01

    Due to limited end-of-life discussions and the absence of palliative care, hospitalisations are frequent at the end of life among nursing home residents in Singapore, resulting in high health-care costs. Our objective was to evaluate the economic impact of Project Care at the End-of-Life for Residents in homes for the Elderly (CARE) programme on nursing home residents compared to usual end-of-life care. DESIGN AND SETTINGS/PARTICIPANTS: Project CARE was introduced in seven nursing homes to provide advance care planning and palliative care for residents identified to be at risk of dying within 1 year. The cases consisted of nursing home residents enrolled in the Project CARE programme for at least 3 months. A historical group of nursing home residents not in any end-of-life care programme was chosen as the matched controls. Cost differences between the two groups were analysed over the last 3 months and final month of life. The final sample comprised 48 Project CARE cases and 197 controls. Compared to the controls, the cases were older with more comorbidities and higher nursing needs. After risk adjustment, Project CARE cases demonstrated per-resident cost savings of SGD$7129 (confidence interval: SGD$4544-SGD$9714) over the last 3 months of life and SGD$3703 (confidence interval: SGD$1848-SGD$5557) over the last month of life (US$1 = SGD$1.3). This study demonstrated substantial savings associated with an end-of-life programme. With a significant proportion of the population in Singapore requiring nursing home care in the near future, these results could assist policymakers and health-care providers in decision-making on allocation of health-care resources.

  7. A practice model for rural district nursing success in end-of-life advocacy care.

    Science.gov (United States)

    Reed, Frances M; Fitzgerald, Les; Bish, Melanie R

    2017-08-24

    The development of a practice model for rural district nursing successful end-of-life advocacy care. Resources to help people live well in the end stages of life in rural areas can be limited and difficult to access. District nurse advocacy may promote end-of-life choice for people living at home in rural Australia. The lack of evidence available internationally to inform practice in this context was addressed by exploratory study. A pragmatic mixed method study approved by the University Faculty Ethics Committee and conducted from March 2014 to August 2015 was used to explore the successful end-of-life advocacy of 98 rural Australian district nurses. The findings and results were integrated then compared with theory in this article to develop concepts for a practice model. The model illustrates rural district nurse advocacy success based on respect for the rights and values of people. Advocacy action is motivated by the emotional responses of nurses to the end-of-life vulnerability people experience. The combination of willing investment in relationships, knowing the rural people and resources, and feeling supported, together enables district nurses to develop therapeutic emotional intelligence. This skill promotes moral agency in reflection and advocacy action to overcome emotional and ethical care challenges of access and choice using holistic assessment, communication, organisation of resources and empowering support for the self-determination of person-centred end-of-life goals. Recommendations are proposed from the theoretical concepts in the model. Testing the model in practice is recommended to gain the perceptions of a broader range of rural people both giving and receiving end-of-life-care. A model developed by gathering and comparing district nursing experiences and understanding using mixed methods and existing theory offers evidence for practice of a philosophy of successful person-centred advocacy care in a field of nursing that lacks specific

  8. How Islam Influences End-of-Life Care: Education for Palliative Care Clinicians.

    Science.gov (United States)

    Leong, Madeline; Olnick, Sage; Akmal, Tahara; Copenhaver, Amanda; Razzak, Rab

    2016-12-01

    According to the Joint Commission, cultural competency is a core skill required for end-of-life care. Religious and cultural beliefs predominantly influence patients' lives, especially during the dying process. Therefore, palliative care clinicians should have at least a basic understanding of major world religions. Islam is a major world religion with 1.7 billion followers. At our institution, a needs assessment showed a lack of knowledge with Islamic teachings regarding end-of-life care. To improve knowledge of clinically relevant Islamic teachings regarding end-of-life care. After consultation with a Muslim chaplain, we identified key topics and created a 10-question pretest. The pretest was administered, followed by a one-hour educational intervention with a Muslim chaplain. Next, a post-test (identical to the pretest) was administered. Eleven palliative care clinicians participated in this study. The average score on the pretest was 6.0 ± 1.2 (mean + SD) (maximum 10). After the educational intervention, the average score improved to 9.6 ± 0.7 (95% CI 2.7-4.4; P Islam influences patients' end-of-life decisions. In this pilot study, a one-hour educational intervention improved knowledge of Islamic teachings regarding end-of-life care. We present a framework for this intervention, which can be easily replicated. We also provide key teaching points on Islam and end-of-life care. Additional research is necessary to determine the clinical effects of this intervention over time and in practice. In the future, we plan to expand the educational material to include other world religions. Copyright © 2016 American Academy of Hospice and Palliative Medicine. Published by Elsevier Inc. All rights reserved.

  9. Network modeling for reverse flows of end-of-life vehicles

    Energy Technology Data Exchange (ETDEWEB)

    Ene, Seval; Öztürk, Nursel

    2015-04-15

    Highlights: • We developed a network model for reverse flows of end-of-life vehicles. • The model considers all recovery operations for end-of-life vehicles. • A scenario-based model is used for uncertainty to improve real case applications. • The model is adequate to real case applications for end-of-life vehicles recovery. • Considerable insights are gained from the model by sensitivity analyses. - Abstract: Product recovery operations are of critical importance for the automotive industry in complying with environmental regulations concerning end-of-life products management. Manufacturers must take responsibility for their products over the entire life cycle. In this context, there is a need for network design methods for effectively managing recovery operations and waste. The purpose of this study is to develop a mathematical programming model for managing reverse flows in end-of-life vehicles’ recovery network. A reverse flow is the collection of used products from consumers and the transportation of these products for the purpose of recycling, reuse or disposal. The proposed model includes all operations in a product recovery and waste management network for used vehicles and reuse for vehicle parts such as collection, disassembly, refurbishing, processing (shredding), recycling, disposal and reuse of vehicle parts. The scope of the network model is to determine the numbers and locations of facilities in the network and the material flows between these facilities. The results show the performance of the model and its applicability for use in the planning of recovery operations in the automotive industry. The main objective of recovery and waste management is to maximize revenue and minimize pollution in end-of-life product operations. This study shows that with an accurate model, these activities may provide economic benefits and incentives in addition to protecting the environment.

  10. Haemodialysis patients and end-of-life decisions: a theory of personal preservation.

    Science.gov (United States)

    Calvin, Amy Olivier

    2004-06-01

    Lack of knowledge about the end-of-life treatment preferences of patients undergoing haemodialysis is problematic in the acute care setting as, often, patients are unable to communicate their treatment wishes effectively and have not previously documented their desires in the form of advance directives. Existing theoretical models offer an incomplete explanation of end-of-life treatment decisions in haemodialysis patients. This paper reports a study exploring decisions about end-of-life treatment (e.g. cardiopulmonary resuscitation, mechanical ventilation) in people with kidney failure undergoing haemodialysis. Grounded theory was used. Theoretical sampling led to selection of 20 haemodialysis patients (11 men and nine women with a mean age of 56) who attended three dialysis outpatient centres in central Texas. They were interviewed about end-of-life treatment plans and the use of advance directives (i.e. living wills and durable powers of attorney for health care). Interviews, transcripts and field notes from the first 12 patients were analysed by making constant comparisons. The remaining eight interviews were used for validation purposes. Data collection and analysis spanned the years 1997-2000. When prompted to think about and discuss end-of-life treatments, haemodialysis patients chose to focus on living rather than dying. A substantive theory of 'personal preservation' was developed. This consists of three phases: knowing the odds for survival, defining individuality (beating the odds, discovering meaning, being optimistic and having faith in a higher force) and personal preservation (being responsible and taking chances). The theory of personal preservation furthers understanding of illness behaviour and the process by which patients make decisions about end-of-life treatments. It can be used to sensitize health care professionals to patients' desires and to enhance patient-professional communication.

  11. Network modeling for reverse flows of end-of-life vehicles

    International Nuclear Information System (INIS)

    Ene, Seval; Öztürk, Nursel

    2015-01-01

    Highlights: • We developed a network model for reverse flows of end-of-life vehicles. • The model considers all recovery operations for end-of-life vehicles. • A scenario-based model is used for uncertainty to improve real case applications. • The model is adequate to real case applications for end-of-life vehicles recovery. • Considerable insights are gained from the model by sensitivity analyses. - Abstract: Product recovery operations are of critical importance for the automotive industry in complying with environmental regulations concerning end-of-life products management. Manufacturers must take responsibility for their products over the entire life cycle. In this context, there is a need for network design methods for effectively managing recovery operations and waste. The purpose of this study is to develop a mathematical programming model for managing reverse flows in end-of-life vehicles’ recovery network. A reverse flow is the collection of used products from consumers and the transportation of these products for the purpose of recycling, reuse or disposal. The proposed model includes all operations in a product recovery and waste management network for used vehicles and reuse for vehicle parts such as collection, disassembly, refurbishing, processing (shredding), recycling, disposal and reuse of vehicle parts. The scope of the network model is to determine the numbers and locations of facilities in the network and the material flows between these facilities. The results show the performance of the model and its applicability for use in the planning of recovery operations in the automotive industry. The main objective of recovery and waste management is to maximize revenue and minimize pollution in end-of-life product operations. This study shows that with an accurate model, these activities may provide economic benefits and incentives in addition to protecting the environment

  12. The PHENIX experiment at RHIC

    Energy Technology Data Exchange (ETDEWEB)

    Tonse, S.R.; Thomas, J.H.

    1993-12-15

    Later this decade the Relativistic Heavy Ion Collider (RHIC) will be built at Brookhaven National Laboratory. Its goal will be to accelerate and collide Au beams at 100 GeV/c in an attempt to create a Quark Gluon Plasma (QGP). The PHENIX detector aims to detect the QGP through its leptonic and hadronic signatures. We describe here its physics capabilities and the details of the apparatus designed to pick out rare leptonic signatures from among hadronic multiplicities of up to 1500 particles per unit of rapidity.

  13. Structural health monitoring tools for late and end of life management of offshore wind turbines

    DEFF Research Database (Denmark)

    McGugan, Malcolm; McKirdy, Scott

    2016-01-01

    The late and end of life stages in an offshore wind turbines (OWT) life cycle have unique features that must be considered. The initial focus on risks associated with start-up issues due to design, manufacturing or process elements gives way to a stable period of operation and maintenance...... margins and the predominance of low redundancy structures, accurate structural health monitoring can play a strong role in safe management and enable increased operating time at end of life and decommissioning. Late life operations of offshore wind farms can pose significant challenges, balancing...

  14. Advancing palliative and end-of-life science in cardiorespiratory populations: The contributions of nursing science.

    Science.gov (United States)

    Grady, Patricia A

    Nursing science has a critical role to inform practice, promote health, and improve the lives of individuals across the lifespan who face the challenges of advanced cardiorespiratory disease. Since 1997, the National Institute of Nursing Research (NINR) has focused attention on the importance of palliative and end-of-life care for advanced heart failure and advanced pulmonary disease through the publication of multiple funding opportunity announcements and by supporting a cadre of nurse scientists that will continue to address new priorities and future directions for advancing palliative and end-of-life science in cardiorespiratory populations. Published by Elsevier Inc.

  15. The enactment stage of end-of-life decision-making for children.

    Science.gov (United States)

    Sullivan, Jane Elizabeth; Gillam, Lynn Heather; Monagle, Paul Terence

    2018-01-11

    Typically pediatric end-of-life decision-making studies have examined the decision-making process, factors, and doctors' and parents' roles. Less attention has focussed on what happens after an end-of-life decision is made; that is, decision enactment and its outcome. This study explored the views and experiences of bereaved parents in end-of-life decision-making for their child. Findings reported relate to parents' experiences of acting on their decision. It is argued that this is one significant stage of the decision-making process. A qualitative methodology was used. Semi-structured interviews were conducted with bereaved parents, who had discussed end-of-life decisions for their child who had a life-limiting condition and who had died. Data were thematically analysed. Twenty-five bereaved parents participated. Findings indicate that, despite differences in context, including the child's condition and age, end-of-life decision-making did not end when an end-of-life decision was made. Enacting the decision was the next stage in a process. Time intervals between stages and enactment pathways varied, but the enactment was always distinguishable as a separate stage. Decision enactment involved making further decisions - parents needed to discern the appropriate time to implement their decision to withdraw or withhold life-sustaining medical treatment. Unexpected events, including other people's actions, impacted on parents enacting their decision in the way they had planned. Several parents had to re-implement decisions when their child recovered from serious health issues without medical intervention. Significance of results A novel, critical finding was that parents experienced end-of-life decision-making as a sequence of interconnected stages, the final stage being enactment. The enactment stage involved further decision-making. End-of-life decision-making is better understood as a process rather than a discrete once-off event. The enactment stage has particular

  16. Clinical review: Ethics and end-of-life care for critically ill patients in China

    OpenAIRE

    Li, Li Bin

    2013-01-01

    Critical care medicine in China has made great advances in recent decades. This has led to an unavoidable issue: end-of-life ethics. With advances in medical technology and therapeutics allowing the seemingly limitless maintenance of life, the exact time of death of an individual patient is often determined by the decision to limit life support. How to care for patients at the end of life is not only a medical problem but also a social, ethical, and legal issue. A lot of factors, besides cult...

  17. The ‘French exception’: the right to continuous deep sedation at the end of life

    Science.gov (United States)

    Horn, Ruth

    2018-01-01

    In 2016, a law came into force in France granting terminally ill patients the right to continuous deep sedation (CDS) until death. This right was proposed as an alternative to euthanasia and presented as the ‘French response’ to problems at the end of life. The law draws a distinction between CDS and euthanasia and other forms of sympton control at the end of life. France is the first country in the world to legislate on CDS. This short report describes the particular context and underlying social values that led to this piece of legislation, and explores its meaning in the wider French context. PMID:29056584

  18. Exploring end-of-life care for South Asian kidney patients: interviewer reflections.

    Science.gov (United States)

    Wilkinson, Emma; Waqar, Muhammad; Gill, Balbir; Hoque, Pina; Jetha, Champa; Bola, Kulwinder Kaur; Mahmood, Riffat; Mahmood, Sultan; Saujani, Rita; Randhawa, Gurch

    2017-03-16

    The reduction of inequalities in access to quality care has been a central tenet of UK health policy. Ethnic minorities may experience additional inequalities because of language and other cultural barriers. This article reports interviewer reflections of conducting interviews with South Asian kidney patients about their experiences of end-of-life care. It explores themes which emerged from the analysis of a focus group held with eight bilingual research interviewers. The relevance of these themes to understanding inequalities and access to end-of-life care is discussed; together with the potential for the research process to contribute to service improvement.

  19. A review on the thermal hydraulic characteristics of the air-cooled

    Indian Academy of Sciences (India)

    In this paper, a review is presented on the experimental investigations and the numerical simulations performed to analyze the thermal-hydraulic performance of the air-cooled heat exchangers. The air-cooled heat exchangers mostly consist of the finned-tube bundles. The primary role of the extended surfaces (fins) is to ...

  20. Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly

    International Nuclear Information System (INIS)

    Liu, X.J.; Cheng, X.

    2009-01-01

    A new fuel assembly design for a thermal supercritical water cooled reactor (SCWR) core is proposed. Compared to the existing fuel assemblies, the present fuel assembly has two-rows of fuel rods between the moderator channels, to achieve a more uniform moderation for all fuel rod cells, and subsequently, a more uniform radial power distribution. In addition, a neutron-kinetics/thermal-hydraulics coupling method is developed, to analyze the neutron-physical and thermal-hydraulic behavior of the fuel assembly designs. This coupling method is based on the sub-channel analysis code COBRA-IV for thermal-hydraulics and the neutron-kinetics code SKETCH-N for neutron-physics. Both the COBRA-IV code and the SKETCH-N code are accordingly modified. An interface is established for the data transfer between these two codes. This coupling method is applied to both the one-row fuel assemblies (previous design) and the two-row fuel assemblies (present design). The performance of the two types of fuel assemblies is compared. The results show clearly that the two-row fuel assembly has more favorable neutron-physical and thermal-hydraulic characteristics than the one-row fuel assembly. The effect of various parameters on the fuel assembly performance is discussed. The coupling method is proven to be well suitable for further applications to SCWR fuel assembly design analysis

  1. Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements

    International Nuclear Information System (INIS)

    Ebert, D.

    1997-07-01

    This is a report on the CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements held at Annapolis, Maryland, USA November 5-8, 1996. This experts' meeting consisted of 140 participants from 21 countries; 65 invited papers were presented. The meeting was divided into five areas: (1) current and prospective plans of thermal hydraulic codes development; (2) current and anticipated uses of thermal-hydraulic codes; (3) advances in modeling of thermal-hydraulic phenomena and associated additional experimental needs; (4) numerical methods in multi-phase flows; and (5) programming language, code architectures and user interfaces. The workshop consensus identified the following important action items to be addressed by the international community in order to maintain and improve the calculational capability: (a) preserve current code expertise and institutional memory, (b) preserve the ability to use the existing investment in plant transient analysis codes, (c) maintain essential experimental capabilities, (d) develop advanced measurement capabilities to support future code validation work, (e) integrate existing analytical capabilities so as to improve performance and reduce operating costs, (f) exploit the proven advances in code architecture, numerics, graphical user interfaces, and modularization in order to improve code performance and scrutibility, and (g) more effectively utilize user experience in modifying and improving the codes

  2. VIPRE-01: a thermal-hydraulic code for reactor cores. Volume 3: programmer's manual (Revision 2)

    International Nuclear Information System (INIS)

    Stewart, C.W.; Koontz, A.S.; Cuta, J.M.; Montgomery, S.D.

    1985-07-01

    The VIPRE thermal-hydraulic computer code for PWR and BWR core analysis has undergone a detailed design review by a committee of experts. A new version of the code, incorporating the committee's recommendations, has been submitted for NRC review and issuance of a safety evaluation report. The changes in the programmers's manual are given

  3. Thermal-hydraulic feedback model to calculate the neutronic cross-section in PWR reactions

    International Nuclear Information System (INIS)

    Santiago, Daniela Maiolino Norberto

    2011-01-01

    In neutronic codes,it is important to have a thermal-hydraulic feedback module. This module calculates the thermal-hydraulic feedback of the fuel, that feeds the neutronic cross sections. In the neutronic co de developed at PEN / COPPE / UFRJ, the fuel temperature is obtained through an empirical model. This work presents a physical model to calculate this temperature. We used the finite volume technique of discretized the equation of temperature distribution, while calculation the moderator coefficient of heat transfer, was carried out using the ASME table, and using some of their routines to our program. The model allows one to calculate an average radial temperature per node, since the thermal-hydraulic feedback must follow the conditions imposed by the neutronic code. The results were compared with to the empirical model. Our results show that for the fuel elements near periphery, the empirical model overestimates the temperature in the fuel, as compared to our model, which may indicate that the physical model is more appropriate to calculate the thermal-hydraulic feedback temperatures. The proposed model was validated by the neutronic simulator developed in the PEN / COPPE / UFRJ for analysis of PWR reactors. (author)

  4. Proceedings of the OECD/CSNI workshop on transient thermal-hydraulic and neutronic codes requirements

    Energy Technology Data Exchange (ETDEWEB)

    Ebert, D.

    1997-07-01

    This is a report on the CSNI Workshop on Transient Thermal-Hydraulic and Neutronic Codes Requirements held at Annapolis, Maryland, USA November 5-8, 1996. This experts` meeting consisted of 140 participants from 21 countries; 65 invited papers were presented. The meeting was divided into five areas: (1) current and prospective plans of thermal hydraulic codes development; (2) current and anticipated uses of thermal-hydraulic codes; (3) advances in modeling of thermal-hydraulic phenomena and associated additional experimental needs; (4) numerical methods in multi-phase flows; and (5) programming language, code architectures and user interfaces. The workshop consensus identified the following important action items to be addressed by the international community in order to maintain and improve the calculational capability: (a) preserve current code expertise and institutional memory, (b) preserve the ability to use the existing investment in plant transient analysis codes, (c) maintain essential experimental capabilities, (d) develop advanced measurement capabilities to support future code validation work, (e) integrate existing analytical capabilities so as to improve performance and reduce operating costs, (f) exploit the proven advances in code architecture, numerics, graphical user interfaces, and modularization in order to improve code performance and scrutibility, and (g) more effectively utilize user experience in modifying and improving the codes.

  5. Thermal-hydraulic assessment of concrete storage cubicle with horizontal 3013 canisters

    Energy Technology Data Exchange (ETDEWEB)

    HEARD, F.J.

    1999-04-08

    The FIDAP computer code was used to perform a series of analyses to assess the thermal-hydraulic performance characteristics of the concrete plutonium storage cubicles, as modified for the horizontal placement of 3013 canisters. Four separate models were developed ranging from a full height model of the storage cubicle to a very detailed standalone model of a horizontal 3013 canister.

  6. Proceedings of transient thermal-hydraulics and coupled vessel and piping system responses 1991

    International Nuclear Information System (INIS)

    Wang, G.Y.; Shin, Y.W.; Moody, F.J.

    1991-01-01

    This book reports on transient thermal-hydraulics and coupled vessel and piping system responses. Topics covered include: nuclear power plant containment designs; analysis of control rods; gate closure of hydraulic turbines; and shock wave solutions for steam water mixtures in piping systems

  7. Validation of a thermal-hydraulic system code on a simple example

    International Nuclear Information System (INIS)

    Kopecek, Vit; Zacha, Pavel

    2014-01-01

    A mathematical model of a U tube was set up and the analytical solution was calculated and used in the assessment of the numerical solutions obtained by using the RELAP5 mod3.3 and TRACE V5 thermal hydraulics codes. A good agreement between the 2 types of calculation was obtained.

  8. Trend analysis of troubles caused by thermal-hydraulic phenomena at nuclear power plants

    International Nuclear Information System (INIS)

    Komatsu, Teruo

    2010-01-01

    The Institute of Nuclear Safety System (INSS) is promoting researches to improve the safety and reliability of nuclear power plants. In the present study, our attention was focused on troubles attributed to thermal-hydraulic phenomena in particular, trend analysis were carried out to learn lessons from these troubles and to prevent their recurrence. Through our survey, we found the following two points. First, many thermal-hydraulics related troubles can be attributed to design faults, since we found some events in foreign countries took place after inadequate facility renovation. To ensure appropriate design verification, it is important to take account of state-of-the-art science and technology and at the same time to pay attention to the compatibility with the initial design concept. Second point, thermal-hydraulic related troubles are common and recurrent to nuclear power plants worldwide. Japanese utilities are planning to introduce some of overseas experiences to their plants, such as power uprate and renovations of aged facilities. It is important to learn lessons from experiences paying close attention continuously to overseas trouble events, including thermal-hydraulics related events, and to use them to improve safety and reliability of nuclear power plants. (author)

  9. A THERMAL-HYDRAULIC SYSTEM FOR THE CONVERSION AND THE STORAGE OF ENERGY

    Directory of Open Access Journals (Sweden)

    MITRAN Tudor

    2016-05-01

    Full Text Available The paper proposes the concept design of a thermal-hydraulic system that converts the thermal energy (from the geothermal water, from the cooling water of power equipment, from exhaust gasses, and so. in hydrostatic energy, that is stored in a hydraulic accumulator. The hydraulic energy can be converted into electrical energy when needed.

  10. Survey of thermal-hydraulic models of commercial nuclear power plants

    International Nuclear Information System (INIS)

    Determan, J.C.; Hendrix, C.E.

    1992-12-01

    A survey of the thermal-hydraulic models of nuclear power plants has been performed to identify the NRC's current analytical capabilities for critical event response. The survey also supports ongoing research for accident management. The results of the survey are presented here. The PC database which records detailed data on each model is described

  11. FFTF thermal-hydraulic testing results affecting piping and vessel component design in LMFBR's

    International Nuclear Information System (INIS)

    Stover, R.L.; Beaver, T.R.; Chang, S.C.

    1983-01-01

    The Fast Flux Test Facility completed four years of pre-operational testing in April 1982. This paper describes thermal-hydraulic testing results from this period which impact piping and vessel component design in LMFBRs. Data discussed are piping flow oscillations, piping thermal stratification and vessel upper plenum stratification. Results from testing verified that plant design limits were met

  12. COBRA-3M: a digital computer code for analyzing thermal-hydraulic behavior in pin bundles

    International Nuclear Information System (INIS)

    Marr, W.W.

    1975-03-01

    The COBRA-3M computer program is a modification of the thermal-hydraulic subchannel-analysis program COBRA-III. It includes detailed thermal models of fuel pin and duct wall. It is especially suitable for analyzing small pin bundles used in in-reactor or out-of-reactor experiments. (U.S.)

  13. Advances in thermal hydraulic and neutronic simulation for reactor analysis and safety

    International Nuclear Information System (INIS)

    Tentner, A.M.; Blomquist, R.N.; Canfield, T.R.; Ewing, T.F.; Garner, P.L.; Gelbard, E.M.; Gross, K.C.; Minkoff, M.; Valentin, R.A.

    1993-01-01

    This paper describes several large-scale computational models developed at Argonne National Laboratory for the simulation and analysis of thermal-hydraulic and neutronic events in nuclear reactors and nuclear power plants. The impact of advanced parallel computing technologies on these computational models is emphasized

  14. Thermal-hydraulic calculation and analysis for QNPP (Qinshan Nuclear Power Plant) containment

    International Nuclear Information System (INIS)

    Xie Hui; Zhou Jie; He Yingchao

    1993-01-01

    Three containment thermal-hydraulic codes CONTEMPT-LT/028, CONTEMPT-4/MOD3 and COMPARE are used to compute and analyse the Qinshan Nuclear Power Plant (QNPP) containment response under LOCA or MSLB conditions. An evaluation of the capability of containment of QNPP is given

  15. Thermal-hydraulic assessment of concrete storage cubicle with horizontal 3013 canisters

    International Nuclear Information System (INIS)

    Heard, F.J.

    1999-01-01

    The FIDAP computer code was used to perform a series of analyses to assess the thermal-hydraulic performance characteristics of the concrete plutonium storage cubicles, as modified for the horizontal placement of 3013 canisters. Four separate models were developed ranging from a full height model of the storage cubicle to a very detailed standalone model of a horizontal 3013 canister

  16. Characteristic thermal-hydraulic problems in NHRs: Overview of experimental investigations and computer codes

    Energy Technology Data Exchange (ETDEWEB)

    Falikov, A A; Vakhrushev, V V; Kuul, V S; Samoilov, O B; Tarasov, G I [OKBM, Nizhny Novgorod (Russian Federation)

    1997-09-01

    The paper briefly reviews the specific thermal-hydraulic problems for AST-type NHRs, the experimental investigations that have been carried out in the RF, and the design procedures and computer codes used for AST-500 thermohydraulic characteristics and safety validation. (author). 13 refs, 10 figs, 1 tab.

  17. Transient thermal-hydraulic/neutronic analysis in a VVER-1000 reactor core

    International Nuclear Information System (INIS)

    Seyed khalil Mousavian; Mohammad Mohsen Ertejaei; Majid Shahabfar

    2005-01-01

    Full text of publication follows: Nowadays, coupled thermal-hydraulic and three-dimensional neutronic codes in order to consider different feedback effects is state of the art subject in nuclear engineering researches. In this study, RELAP5/COBRA and WIMS/CITATION codes are implemented to investigate the VVER-1000 reactor core parameters during Large Break Loss of Coolant Accident (LB-LOCA). In a LB-LOCA, the primary side pressure, coolant density and fuel temperature strongly decrease but the cladding temperature experiences a strong peak. For this purpose, the RELAP5 Best Estimate (BE) system code is used to simulate the LB-LOCA analysis in VVER-1000 nuclear thermal-hydraulic loops. Also, the modified COBRA-IIIc software as a sub-channel analysis code is applied for modeling of VVER-1000 reactor core. Moreover, WIMS and CITATION as a cross section and 3-D neutron flux codes are coupled with thermal-hydraulic codes with the aim of consider the spatial effects through the reactor core. For this reason, suitable software is developed to link and speed up the coupled thermalhydraulic and three-dimensional neutronic calculations. This software utilizes of external coupling concept in order to integrate thermal-hydraulic and neutronic calculations. (authors)

  18. Evaluation of thermal-hydraulic parameter uncertainties in a TRIGA research reactor

    International Nuclear Information System (INIS)

    Mesquita, Amir Z.; Costa, Antonio C.L.; Ladeira, Luiz C.D.; Rezende, Hugo C.; Palma, Daniel A.P.

    2015-01-01

    Experimental studies had been performed in the TRIGA Research Nuclear Reactor of CDTN/CNEN to find out the its thermal hydraulic parameters. Fuel to coolant heat transfer patterns must be evaluated as function of the reactor power in order to assess the thermal hydraulic performance of the core. The heat generated by nuclear fission in the reactor core is transferred from fuel elements to the cooling system through the fuel-cladding (gap) and the cladding to coolant interfaces. As the reactor core power increases the heat transfer regime from the fuel cladding to the coolant changes from single-phase natural convection to subcooled nucleate boiling. This paper presents the uncertainty analysis in the results of the thermal hydraulics experiments performed. The methodology used to evaluate the propagation of uncertainty in the results was done based on the pioneering article of Kline and McClintock, with the propagation of uncertainties based on the specification of uncertainties in various primary measurements. The uncertainty analysis on thermal hydraulics parameters of the CDTN TRIGA fuel element is determined, basically, by the uncertainty of the reactor's thermal power. (author)

  19. PHENIX central arm tracking detectors

    International Nuclear Information System (INIS)

    Adcox, K.; Ajitanand, N.N.; Alexander, J.; Autrey, D.; Averbeck, R.; Azmoun, B.; Barish, K.N.; Baublis, V.V.; Belkin, R.; Bhaganatula, S.; Biggs, J.C.; Borland, D.; Botelho, S.; Bryan, W.L.; Burward-Hoy, J.; Butsyk, S.A.; Chang, W.C.; Christ, T.; Dietzsch, O.; Drees, A.; Rietz, R. du; El Chenawi, K.; Evseev, V.A.; Fellenstein, J.; Ferdousi, T.; Fraenkel, Z.; Franz, A.; Fung, S.Y.; Gannon, J.; Garpman, S.; Godoi, A.L.; Greene, S.V.; Gustafsson, H.-A.; Harder, J.; Hemmick, T.K.; Heuser, J.M.; Holzmann, W.; Hutter, R.; Issah, M.; Ivanov, V.I.; Jacak, B.V.; Jagadish, U.; Jia, J.; Johnson, S.C.; Kandasamy, A.; Kann, M.R.; Kelley, M.A.; Khanzadeev, A.V.; Khomutnikov, A.; Komkov, B.G.; Kopytine, M.L.; Kotchenda, L.; Kotchetkov, D.; Kozlov, V.S.; Kravtsov, P.A.; Kudin, L.G.; Kuriatkov, V.V.; Lacey, R.; Lauret, J.; Lebedev, A.; Lebedev, V.D.; Li, X.H.; Libby, B.; Liccardi, W.; Machnowski, R.; Mahon, J.; Markushin, D.G.; Matathias, F.; Marx, M.D.; Messer, F.; Miftakhov, N.M.; Milan, J.; Miller, T.E.; Milov, A.; Minuzzo, K.; Mioduszewski, S.; Mitchell, J.T.; Muniruzzamann, M.; Nandi, B.K.; Negrin, J.; Nilsson, P.; Nystrand, J.; O'Brien, E.; O'Connor, P.; Oskarsson, A.; Oesterman, L.; Otterlund, I.; Pancake, C.E.; Pantuev, V.S.; Petersen, R.; Pinkenburg, C.H.; Pisani, R.P.; Purwar, A.K.; Rankowitz, S.; Ravinovich, I.; Riabov, V.G.; Riabov, Yu.G.; Rosati, M.; Rose, A.A.; Roschin, E.V.; Samsonov, V.M.; Sangster, T.C.; Seto, R.; Silvermyr, D.; Sivertz, M.; Smith, M.; Solodov, G.P.; Stenlund, E.; Takagui, E.M.; Tarakanov, V.I.; Tarasenkova, O.P.; Thomas, J.L.; Trofimov, V.A.; Tserruya, I.; Tydesjoe, H.; Velkovska, J.; Velkovsky, M.; Vishnevskii, V.I.; Vorobyov, A.A.; Vznuzdaev, E.A.; Vznuzdaev, M.; Wang, H.Q.; Weimer, T.; Wolniewicz, K.; Wu, J.; Xie, W.; Young, G.R.

    2003-01-01

    The PHENIX tracking system consists of Drift Chambers (DC), Pad Chambers (PC) and the Time Expansion Chamber (TEC). PC1/DC and PC2/TEC/PC3 form the inner and outer tracking units, respectively. These units link the track segments that transverse the RICH and extend to the EMCal. The DC measures charged particle trajectories in the r-phi direction to determine p T of the particles and the invariant mass of particle pairs. The PCs perform 3D spatial point measurements for pattern recognition and longitudinal momentum reconstruction and provide spatial resolution of a few mm in both r-phi and z. The TEC tracks particles passing through the region between the RICH and the EMCal. The design and operational parameters of the detectors are presented and running experience during the first year of data taking with PHENIX is discussed. The observed spatial and momentum resolution is given which imposes a limitation on the identification and characterization of charged particles in various momentum ranges

  20. Patient-Clinician Communication About End-of-Life Care in Patients With Advanced Chronic Organ Failure During One Year.

    Science.gov (United States)

    Houben, Carmen H M; Spruit, Martijn A; Schols, Jos M G A; Wouters, Emiel F M; Janssen, Daisy J A

    2015-06-01

    Patient-clinician communication is an important prerequisite to delivering high-quality end-of-life care. However, discussions about end-of-life care are uncommon in patients with advanced chronic organ failure. The aim was to examine the quality of end-of-life care communication during one year follow-up of patients with advanced chronic organ failure. In addition, we aimed to explore whether and to what extent quality of communication about end-of-life care changes toward the end of life and whether end-of-life care communication is related to patient-perceived quality of medical care. Clinically stable outpatients (n = 265) with advanced chronic obstructive pulmonary disease, chronic heart failure, or chronic renal failure were visited at home at baseline and four, eight, and 12 months after baseline to assess quality of end-of-life care communication (Quality of Communication questionnaire). Two years after baseline, survival status was assessed, and if patients died during the study period, a bereavement interview was done with the closest relative. One year follow-up was completed by 77.7% of the patients. Quality of end-of-life care communication was rated low at baseline and did not change over one year. Quality of end-of-life care communication was comparable for patients who completed two year follow-up and patients who died during the study. The correlation between quality of end-of-life care communication and satisfaction with medical treatment was weak. End-of-life care communication is poor in patients with chronic organ failure and does not change toward the end of life. Future studies should develop an intervention aiming at initiating high-quality end-of-life care communication between patients with advanced chronic organ failure and their clinicians. Copyright © 2015 American Academy of Hospice and Palliative Medicine. Published by Elsevier Inc. All rights reserved.

  1. Quantification of LOCA core damage frequency based on thermal-hydraulics analysis

    International Nuclear Information System (INIS)

    Cho, Jaehyun; Park, Jin Hee; Kim, Dong-San; Lim, Ho-Gon

    2017-01-01

    Highlights: • We quantified the LOCA core damage frequency based on the best-estimated success criteria analysis. • The thermal-hydraulic analysis using MARS code has been applied to Korea Standard Nuclear Power Plants. • Five new event trees with new break size boundaries and new success criteria were developed. • The core damage frequency is 5.80E−07 (/y), which is 12% less than the conventional PSA event trees. - Abstract: A loss-of-coolant accident (LOCA) has always been significantly considered one of the most important initiating events. However, most probabilistic safety assessment models, up to now, have undoubtedly adopted the three groups of LOCA, and even an exact break size boundary that used in WASH-1400 reports was published in 1975. With an awareness of the importance of a realistic PSA for a risk-informed application, several studies have tried to find the realistic thermal-hydraulic behavior of a LOCA, and improve the PSA model. The purpose of this research is to obtain realistic results of the LOCA core damage frequency based on a success criteria analysis using the best-estimate thermal-hydraulics code. To do so, the Korea Standard Nuclear Power Plant (KSNP) was selected for this study. The MARS code was used for a thermal hydraulics analysis and the AIMS code was used for the core damage quantification. One of the major findings in the thermal hydraulics analysis was that the decay power is well removed by only a normal secondary cooling in LOCAs of below 1.4 in and by only a high pressure safety injection in LOCAs of 0.8–9.4 in. Based on the thermal hydraulics results regarding new break size boundaries and new success criteria, five new event trees (ETs) were developed. The core damage frequency of new LOCA ETs is 5.80E−07 (/y), which is 12% less than the conventional PSA ETs. In this research, we obtained not only thermal-hydraulics characteristics for the entire break size of a LOCA in view of the deterministic safety

  2. Quantification of LOCA core damage frequency based on thermal-hydraulics analysis

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Jaehyun, E-mail: chojh@kaeri.re.kr; Park, Jin Hee; Kim, Dong-San; Lim, Ho-Gon

    2017-04-15

    Highlights: • We quantified the LOCA core damage frequency based on the best-estimated success criteria analysis. • The thermal-hydraulic analysis using MARS code has been applied to Korea Standard Nuclear Power Plants. • Five new event trees with new break size boundaries and new success criteria were developed. • The core damage frequency is 5.80E−07 (/y), which is 12% less than the conventional PSA event trees. - Abstract: A loss-of-coolant accident (LOCA) has always been significantly considered one of the most important initiating events. However, most probabilistic safety assessment models, up to now, have undoubtedly adopted the three groups of LOCA, and even an exact break size boundary that used in WASH-1400 reports was published in 1975. With an awareness of the importance of a realistic PSA for a risk-informed application, several studies have tried to find the realistic thermal-hydraulic behavior of a LOCA, and improve the PSA model. The purpose of this research is to obtain realistic results of the LOCA core damage frequency based on a success criteria analysis using the best-estimate thermal-hydraulics code. To do so, the Korea Standard Nuclear Power Plant (KSNP) was selected for this study. The MARS code was used for a thermal hydraulics analysis and the AIMS code was used for the core damage quantification. One of the major findings in the thermal hydraulics analysis was that the decay power is well removed by only a normal secondary cooling in LOCAs of below 1.4 in and by only a high pressure safety injection in LOCAs of 0.8–9.4 in. Based on the thermal hydraulics results regarding new break size boundaries and new success criteria, five new event trees (ETs) were developed. The core damage frequency of new LOCA ETs is 5.80E−07 (/y), which is 12% less than the conventional PSA ETs. In this research, we obtained not only thermal-hydraulics characteristics for the entire break size of a LOCA in view of the deterministic safety

  3. Medical futility and end-of-life care | Sidler | South African Medical ...

    African Journals Online (AJOL)

    treating physician is responsible for guiding this process by demonstrating sensitivity and compassion, respecting the values of patients, their families and the medical staff. The need for training to equip medical staff to take responsibility as empathetic participants in end-of-life decision-making is underscored. South African ...

  4. Bereaved relatives' perspectives of the patient's oral intake towards the end of life: a qualitative study.

    NARCIS (Netherlands)

    Raijmakers, N.J.H.; Clark, J.B.; Zuylen, L. van; Allan, S.G.; Heide, A. van der

    2013-01-01

    Background: Patients approaching death often have a decreasing oral intake, which can be distressing for relatives. Little is known about the relatives' experiences with and perceptions of oral intake at the end of life. Aim:This study aims to contribute to a more thorough understanding of

  5. Medical futility in children's nursing: making end-of-life decisions.

    Science.gov (United States)

    Brien, Irene O; Duffy, Anita; Shea, Ellen O

    Caring for infants at end of life is challenging and distressing for parents and healthcare professionals, especially in relation to making decisions regarding withholding or withdrawal of treatment. The concept of medical futility must be considered under these circumstances. Parents and healthcare professionals should be involved together in making these difficult decisions. However, for some parents, emotions and guilt often are unbearable and, understandably, parents can be reluctant to make a decision. Despite the recognition of parental autonomy, if parents disagree with a decision made by medical staff, the case will be referred to and solved by the courts. The courts' decisions are often based on the best interest of the child. In this article, the authors discuss the concepts of 'parental autonomy' and 'the child's best interests' when determining medical futility for infants or neonates. The role of the nurse when caring for the dying child and their family is multifaceted. While nurses do not have a legitimate role in decision making at the end of life, it is often nurses who, through their advocacy role, inform doctors about parents' wishes and it is often nurses who support parents during this difficult time. Furthermore, nurses caring for dying children should be familiar to the family, experienced in end-of-life care and comfortable talking to parents about death and dying and treatment choices. Children's nurses therefore require advanced communication skills and an essential understanding of the ethical and legal knowledge relating to medical futility in end-of-life children's nursing.

  6. What parents want from doctors in end-of-life decision-making for children.

    Science.gov (United States)

    Sullivan, J; Monagle, P; Gillam, L

    2014-03-01

    End-of-life decision-making is difficult for everyone involved, as many studies have shown. Within this complexity, there has been little information on how parents see the role of doctors in end-of-life decision-making for children. This study aimed to examine parents' views and experiences of end-of-life decision-making. A qualitative method with a semistructured interview design was used. Parent participants were living in the community. Twenty-five bereaved parents. Parents reported varying roles taken by doctors: being the provider of information without opinion; giving information and advice as to the decision that should be taken; and seemingly being the decision maker for the child. The majority of parents found their child's doctor enabled them to be the ultimate decision maker for their child, which was what they very clearly wanted to be, and consequently enabled them to exercise their parental autonomy. Parents found it problematic when doctors took over decision-making. A less frequently reported, yet significant role for doctors was to affirm decisions after they had been made by parents. Other important aspects of the doctor's role were to provide follow-up support and referral. Understanding the role that doctors take in end-of-life decisions, and the subsequent impact of that role from the perspective of parents can form the basis of better informed clinical practice.

  7. Raising end of life care issues for patients with learning disabilities.

    Science.gov (United States)

    Sander, Ruth

    2012-11-30

    This qualitative study explored the views of three learning disability nurses, and three district nurses, caring for people with learning disabilities at the end of their lives. Although they saw some good practice, the nurses identified several difficulties associated with end of life care.

  8. Pleurodesis for effusions in pediatric oncology patients at end of life

    Energy Technology Data Exchange (ETDEWEB)

    Hoffer, Fredric A. [St. Jude Children' s Research Hospital, Department of Radiological Sciences, Memphis, TN (United States); Children' s Hospital and Regional Medical Center, Department of Radiology, R-5438, Seattle, WA (United States); Hancock, Michael L.; Rai, Shesh N. [St. Jude Children' s Research Hospital, Department of Biostatistics, Memphis, TN (United States); Hinds, Pamela S. [St. Jude Children' s Research Hospital, Division of Nursing Research, Memphis, TN (United States); Oigbokie, Nikita [St. Jude Children' s Research Hospital, Department of Radiological Sciences, Memphis, TN (United States); Rao, Bhaskar [St. Jude Children' s Research Hospital, Department of Surgery, Memphis, TN (United States)

    2007-03-15

    Pleurodesis for end-of-life care has been used in adults for decades, but little is known about the usefulness of this technique in improving the quality of care for pediatric patients. To assess whether intractable pleural effusions in pediatric oncology patients at end of life could be sufficiently relieved by pleurodesis. Eleven pleurodeses were performed with doxycycline in seven pediatric cancer patients (age 3-21 years) with intractable pleural effusions at the end of life. Five patients had unilateral pleurodeses and two had a unilateral followed by bilateral pleurodeses. Respiratory rates decreased in all seven patients (P = 0.016) and aeration improved significantly after chest tube placement (P = 0.033). The chest tubes were placed a median of 1 day before pleurodesis. Eight of nine chest tubes (89%) were removed before discharge at a median of 3 days after pleurodesis. Pain secondary to the pleurodesis lasted 1 day or less. Improvement in the respiratory rate remained after pleurodesis and chest tube removal (P = 0.031). Five of seven patients (70%) were able to leave the hospital to return home. The five patients discharged lived 10 to 49 days (median 19 days) after discharge. Pediatric oncology patients with intractable effusions at end of life can have respiratory benefit from pleurodeses and, as a result, are more likely to return home for terminal care. (orig.)

  9. Rural-Urban Differences in End-of-Life Nursing Home Care: Facility and Environmental Factors

    Science.gov (United States)

    Temkin-Greener, Helena; Zheng, Nan Tracy; Mukamel, Dana B.

    2012-01-01

    Purpose of the study: This study examines urban-rural differences in end-of-life (EOL) quality of care provided to nursing home (NH) residents. Data and Methods: We constructed 3 risk-adjusted EOL quality measures (QMs) for long-term decedent residents: in-hospital death, hospice referral before death, and presence of severe pain. We used…

  10. The new challenges of end-of-life tyres management systems: A Spanish case study

    International Nuclear Information System (INIS)

    Uruburu, Ángel; Ponce-Cueto, Eva; Cobo-Benita, José Ramón; Ordieres-Meré, Joaquín

    2013-01-01

    Highlights: ► Impact of the implementation of the Directive 2008/98/EC in Spain for end-of-life tyres. ► Characterization of the reverse supply chain for collecting, recovering, and treating end-of-life tyres. ► Identification of challenges to be coped and issues to be covered. ► Potential new applications for end-of-life tyres and development of new management related strategies. - Abstract: Directive 2008/98/EC released by the European Union represents a significant step forward in all relevant aspects of waste management. Under the already established, extended produced responsibility (EPR) principle, new policies have been enunciated to continuously achieve better overall environmental performance of key products throughout their life phases. This paper discusses how the directive is being articulated in Spain by the main integrated management system (IMS) for end-of-life (EOL) tyres since its creation in 2006. Focusing on the IMS technological, economic and legal aspects, the study provides a global perspective and evaluation of how the IMS is facing the current issues to resolve, the new challenges that have appeared and the management vision for the coming years

  11. The use of theory in qualitative approaches to research: application in end-of-life studies.

    Science.gov (United States)

    Wu, Hung-Lan; Volker, Deborah L

    2009-12-01

    This paper is a report of an analysis of the use of theory in qualitative approaches to research as exemplified in qualitative end-of-life studies. Nurses researchers turn to theory to conceptualize research problems and guide investigations. However, researchers using qualitative approaches do not consistently articulate how theory has been applied, and no clear consensus exists regarding the appropriate application of theory in qualitative studies. A review of qualitative, end-of-life studies is used to illustrate application of theory to study design and findings. A review of theoretical literature was carried out, focusing on definitions and use of theory in qualitative end-of-life studies published in English between 1990 and 2008. The term 'theory' continues to be used in a variety of ways by theorists and researchers. Within the reviewed end-of-life studies, the use of theory included theory creation or provision of a comparative framework for data analysis and interpretation. Implications for nursing. Nurses who conduct qualitative studies should examine the philosophical and theoretical bases of their selected methodological approach, articulate a theoretical framework that fits the phenomenon being studied, and adopt a critical, flexible and creative attitude when applying theory to a study. Theory can be put to several uses in qualitative inquiry and should guide nurse researchers as they develop and implement their studies. Nurse educators who teach qualitative approaches to research should emphasize a variety of ways to incorporate theory in qualitative designs.

  12. Learning end-of-life care within a constructivist model: Undergraduate nursing students’ experiences

    Directory of Open Access Journals (Sweden)

    Anna E. van der Wath

    2015-11-01

    Full Text Available Background: Although nursing education aims to equip nursing students to provide care to dying patients and their families, nurses often feel ill-prepared to cope with the emotional labour involved in end-of-life care. Objectives: The aim of the study was to explore and describe nursing students’ experiences of end-of-life care through experiential learning within a constructivist educational model. Method: A qualitative, descriptive design was used. As part of introducing experiential learning, innovative educational practices were initiated during a second year level undergraduate nursing module on end-of-life care. Qualitative data on second-year nursing students’ experiences were collected through written reflections and analysed using open coding. Results: The themes that emerged revealed participants’ sensory and emotional experiences during the learning opportunities. Participants reflected on what they learnt and clarified their values related to death and dying. They indicated how they would apply the new meanings constructed in clinical practice. Conclusion: A constructivist educational model of experiential learning holds potential to enhance value clarification and nursing students’ sensory and emotional awareness of death and dying. Experiential learning is recommended to develop nursing students’ competency inproviding end-of-life care.

  13. When Safe Oral Feeding Is Threatened: End-of-Life Options and Decisions

    Science.gov (United States)

    Groher, Michael E.; Groher, Tammy Peutz

    2012-01-01

    Managing one's dysphagia at the end-of-life is challenging for the patient and the medical care team. Decisions surrounding oral feeding safety and the use of artificially administered hydration and nutrition require the medical care team to provide its best advice, taking into consideration the patient's health-related goals and the impact the…

  14. Learning About End-of-Life Care in Nursing-A Global Classroom Educational Innovation.

    Science.gov (United States)

    Bailey, Cara; Hewison, Alistair; Orr, Shelly; Baernholdt, Marianne

    2017-11-01

    Teaching nursing students how to provide patient-centered end-of-life care is important and challenging. As traditional face-to-face classroom teaching is increasingly supplanted by digital technology, this provides opportunities for developing new forms of end-of-life care education. The aim of this article is to examine how a global classroom was developed using online technology to enhance nursing students' learning of end-of-life care in England and the United States. The PDSA (Plan-Do-Study-Act) quality improvement approach was used to guide the design and delivery of this curriculum innovation. The global classroom enhanced the educational experience for students. Teaching needs to be inclusive, focused, and engaging; the virtual platform must be stable and support individual learning, and learning needs to be collaborative and authentic. These findings can be used to inform the integration of similar approaches to end-of-life care education in other health care professional preparation programs. [J Nurs Educ. 2017;56(11):688-691.]. Copyright 2017, SLACK Incorporated.

  15. Pleurodesis for effusions in pediatric oncology patients at end of life

    International Nuclear Information System (INIS)

    Hoffer, Fredric A.; Hancock, Michael L.; Rai, Shesh N.; Hinds, Pamela S.; Oigbokie, Nikita; Rao, Bhaskar

    2007-01-01

    Pleurodesis for end-of-life care has been used in adults for decades, but little is known about the usefulness of this technique in improving the quality of care for pediatric patients. To assess whether intractable pleural effusions in pediatric oncology patients at end of life could be sufficiently relieved by pleurodesis. Eleven pleurodeses were performed with doxycycline in seven pediatric cancer patients (age 3-21 years) with intractable pleural effusions at the end of life. Five patients had unilateral pleurodeses and two had a unilateral followed by bilateral pleurodeses. Respiratory rates decreased in all seven patients (P = 0.016) and aeration improved significantly after chest tube placement (P = 0.033). The chest tubes were placed a median of 1 day before pleurodesis. Eight of nine chest tubes (89%) were removed before discharge at a median of 3 days after pleurodesis. Pain secondary to the pleurodesis lasted 1 day or less. Improvement in the respiratory rate remained after pleurodesis and chest tube removal (P = 0.031). Five of seven patients (70%) were able to leave the hospital to return home. The five patients discharged lived 10 to 49 days (median 19 days) after discharge. Pediatric oncology patients with intractable effusions at end of life can have respiratory benefit from pleurodeses and, as a result, are more likely to return home for terminal care. (orig.)

  16. End of life care in chronic obstructive pulmonary disease: in search of a good death

    Directory of Open Access Journals (Sweden)

    Anna Spathis

    2008-03-01

    Full Text Available Anna Spathis, Sara BoothPalliative Care Service, Cambridge University Hospitals NHS Foundation Trust, Cambridge, England, UKAbstract: Chronic obstructive pulmonary disease (COPD is an incurable, progressive illness that is the fourth commonest cause of death worldwide. Death tends to occur after a prolonged functional decline associated with uncontrolled symptoms, emotional distress and social isolation. There is increasing evidence that the end of life needs of those with advanced COPD are not being met by existing services. Many barriers hinder the provision of good end of life care in COPD, including the inherent difficulties in determining prognosis. This review provides an evidence-based approach to overcoming these barriers, summarising current evidence and highlighting areas for future research. Topics include end of life needs, symptom control, advance care planning, and service development to improve the quality of end of life care.Keywords: chronic obstructive pulmonary disease (MeSH, palliative care (MeSH, dyspnoea (MeSH, advance care planning (MeSH

  17. Dying means suffocating: perceptions of people living with severe COPD facing the end of life.

    Science.gov (United States)

    Hall, Sylvie; Legault, Alan; Côté, José

    2010-09-01

    The purpose of this research was to describe the perceptions of people living with severe chronic obstructive pulmonary disease (COPD) with respect to the end of life. For this descriptive exploratory qualitative study, semi-structured interviews were conducted with six participants suffering from severe COPD hospitalized in the past year following an exacerbation episode. The data were analyzed using the method developed by Miles and Huberman (2003), which comprises three main steps: data reduction, data display, and conclusion drawing/verification. The analysis yielded four themes that reflect the perceptions of participants with respect to the end of life, namely: living and seeing oneself decline, living and preparing to die, dying of COPD means suffocating, and dying in hospital surrounded by family and friends. What emerges from the study is that persons living with severe COPD wish to die without suffocating, in hospital, surrounded by family and friends, all the while hoping to go on living. This study contributes to a more comprehensive understanding of the end-of-life experience. It shows the importance of accompanying these persons properly towards the end of life and at the moment of dying. The study proposes a series of avenues for future research and makes recommendations for practice.

  18. Quantitative assessment of material composition of end-of-life ships using onboard documentation

    NARCIS (Netherlands)

    Jain, K.P.; Pruyn, J.F.J.; Hopman, J.J.

    2016-01-01

    Ship recycling yards around the world offer a price to the ship owners for buying an obsolete vessel to demolish and recycle based on the ship's end-of-life weight. The offer price is mainly based on the type of ship and the estimated quantity of steel available. The steel weight estimation, in

  19. Export, metal recovery and the mobile phone end-of-life ecosystem

    NARCIS (Netherlands)

    Bollinger, L.A.; Blass, V.

    2012-01-01

    Against a background of rapidly growing mobile phone consumption in developing and emerging economies, falling use times and looming metal scarcity, finding better ways to deal with end-of-life (EoL) phones is imperative. The current dynamic in which large numbers of EoL phones are exported from

  20. Caring for people at the end of life: Iranian oncology nurses′ experiences

    Directory of Open Access Journals (Sweden)

    Sedigheh Iranmanesh

    2009-01-01

    Conclusion: The study suggests that the nurses′ success in caring for people at the end of life is reliant on their interpersonal caring relationship. Facilitating such relationship requires the establishment of palliative care unit, incorporation of palliative care into undergraduate nursing studies, and cultural preparation through public education.

  1. Peaceful Death: Recommended Competencies and Curricular Guidelines for End-of-Life Nursing Care.

    Science.gov (United States)

    American Association of Colleges of Nursing, Washington, DC.

    A group of health care ethicists and palliative care experts convened by the American Association of Colleges of Nursing developed a set of competencies that should be achieved through nursing curricula. The purpose of the 15 competency statements is to assist nurse educators in incorporating end-of-life content into nursing curricula. Every…

  2. A Framework for Categorizing Social Interactions Related to End-of-Life Care in Nursing Homes

    Science.gov (United States)

    Bern-Klug, Mercedes

    2009-01-01

    Purpose: Almost half of people age 85 and older who die annually in the United States die as nursing home residents, yet because it is not always clear who is close to death, not all residents who might benefit from end-of-life care receive it. The purpose of this study is to develop a framework for organizing social interactions related to…

  3. Health Care Decisions at the End of Life: Theological and Ethical Foundations for Decision Making.

    Science.gov (United States)

    Allegretti, Joseph G.

    This paper provides a framework for making sense of perplexing problems surrounding issues of death and dying by exploring the theological and ethical background to health care decision making at the end of life. The paper first examines several of the basic principles that theologians and secular ethicists employ when analyzing such questions.…

  4. [State policy at the end of life. The transformation of medical deontology].

    Science.gov (United States)

    Serrano Ruiz-Calderón, José Miguel

    2012-01-01

    The contemporary state invades privacy in ways that affect even the end of life process. It develops public policies that can affect medical ethics. This limitation of power leaves the doctor's attention to the profession and may become a convenient code.

  5. Factors Affecting Patients' Preferences for and Actual Discussions About End-of-Life Care.

    Science.gov (United States)

    Fakhri, Shoaib; Engelberg, Ruth A; Downey, Lois; Nielsen, Elizabeth L; Paul, Sudiptho; Lahdya, Alexandria Z; Treece, Patsy D; Curtis, J Randall

    2016-09-01

    Discussions about end-of-life care are often difficult for patients and clinicians, and inadequate communication poses a barrier to patients receiving the care they desire. To understand factors that facilitate end-of-life care discussions that guide interventions to improve care. We examined baseline data from an ongoing randomized trial to evaluate associations between patients' self-reported desire for, and occurrence of, discussions about end-of-life care and factors influencing these discussions. Factors included emotional symptoms and barriers and facilitators to discussions. The sample included patients with serious illness (n = 473) and their primary or specialty care clinicians (n = 128). Regression analyses were adjusted for confounders and clustered patients under clinicians. Patients who endorsed each of three barriers to discussions were less likely to have had a discussion with their clinician (P-values ranging from communication about end-of-life care is associated with patient factors including communication barriers and facilitators and symptoms of depression and anxiety. Understanding these factors may facilitate design of effective communication interventions. Copyright © 2016 American Academy of Hospice and Palliative Medicine. Published by Elsevier Inc. All rights reserved.

  6. Euthanasia and other end-of-life decisions: a mortality follow-back study in Belgium

    NARCIS (Netherlands)

    Block, L.; Deschepper, R.; Bilsen, J.J.; Bossuyt, N.; Casteren, van V.; Deliens, L.H.J.

    2009-01-01

    BACKGROUND: This study compares prevalence and types of medical end-of-life decisions between the Dutch-speaking and French-speaking communities of Belgium. This is the first nationwide study that can make these comparisons and the first measurement after implementation of the euthanasia law (2002).

  7. Factors That Impact End-of-Life Decision Making in African Americans With Advanced Cancer

    Science.gov (United States)

    Campbell, Cathy L.; Williams, Ishan C.; Orr, Tamara

    2013-01-01

    Significance African Americans with cancer are less likely to use hospice services and more likely to die in the hospital than white patients with the same diagnosis. However, there is much that is not understood about the factors that lead African Americans to choose options for end-of-life care. Design A qualitative, descriptive design was used in this pilot study. Methods Interviews were conducted with two groups of African Americans with advanced-stage cancer (people enrolled in hospice and those who were not under hospice care). Findings End-of-life decisions were primarily guided by clinical factors, the patient-related physical, emotional, and cognitive symptoms that are sequelae of the underlying disease or medical treatments. The physician was the healthcare provider most likely to be involved in decision making with patients, family members, and caregivers. Individual factors, such as personal beliefs, influenced end-of-life decision making. Religion and spirituality were a topic in many interviews, but they did not consistently influence decision making. Discussion Future studies should include interviews with family members, caregivers, and healthcare professionals so that factors that impact end-of-life decision making can be fully described. Strategies to facilitate recruitment will need to be added to future protocols. PMID:23645999

  8. [The nursing role and ethical dimension of end of life care].

    Science.gov (United States)

    Daydé, Marie-Claude

    2016-02-01

    Supporting people in situations of precarity at the end of life is often fraught with complex problems, where one form of vulnerability amplifies another. This complexity requires interdisciplinary support, around the nursing care, to reflect together on the meaning of the action taken in an ethical approach. Copyright © 2015 Elsevier Masson SAS. All rights reserved.

  9. Experiences and attitudes towards end-of-life decisions amongst Danish physicians

    DEFF Research Database (Denmark)

    Folker, Anna Paldam; Holtug, Nils; Jensen, Annette B

    1996-01-01

    In this survey we have investigated the experiences and attitudes of Danish physicians regarding end-of-life decisions. Most respondents have made decisions that involve hastening the death of a patient, and almost all find it acceptable to do so. Such decisions are made more often, and considered...

  10. Talking about end-of-life care in a timely manner

    NARCIS (Netherlands)

    Smeenk, Frank W. J. M.; Schrijver, Laurien A; van Bavel, Hennie C. J.; van de Laar, Eric F. J.

    2017-01-01

    In 2014, a group of physicians of the Catharina Hospital in Eindhoven (The Netherlands) started a project called “Talking about end-of-life care in a timely manner”. Just like others in the country, the Eindhoven group noticed that regularly, very frail elderly people were admitted to hospital in

  11. Positive emotion communication: Fostering well-being at end of life.

    Science.gov (United States)

    Terrill, Alexandra L; Ellington, Lee; John, Kevin K; Latimer, Seth; Xu, Jiayun; Reblin, Maija; Clayton, Margaret F

    2018-04-01

    Little is known about positive emotion communication (PEC) in end-of-life care. This study aims to identify types and patterns of PEC among hospice nurses, caregivers, and patients. A coding system based on positive psychology theory was applied as a secondary analysis to audio recordings of hospice nurse home visits with cancer patients and family caregivers, collected as part of a prospective longitudinal study. Eighty recordings (4 visits from 20 triads) were coded for humor, connection, praise, positive focus, gratitude, taking joy/savoring, and perfunctory statements. Descriptive statistics revealed the greatest proportion of PEC was made by nurses. Humor was most frequently used across all speakers. Cluster analysis revealed four PEC visit types: Savor/Take Joy; Humor; Perfunctory; and Other-focused Expressions of Positive Emotions. Linear mixed effect regression was used to estimate the trajectory of PEC over time, but no significant change was found. We found that positive emotions are common in nurse, caregiver and patient communication at end-of-life and do not decline closer to death. This study is among the first to explore PEC at end-of-life, and offers a way to bring strengths-based approaches into end of life communication research. Copyright © 2017 Elsevier B.V. All rights reserved.

  12. The end-of-life phase of high-grade glioma patients: a systematic review

    NARCIS (Netherlands)

    Sizoo, Eefje M.; Pasman, H. Roeline W.; Dirven, Linda; Marosi, Christine; Grisold, Wolfgang; Stockhammer, Günther; Egeter, Jonas; Grant, Robin; Chang, Susan; Heimans, Jan J.; Deliens, Luc; Reijneveld, Jaap C.; Taphoorn, Martin J. B.

    2014-01-01

    High-grade gliomas (HGG) are rare and incurable; yet, these neoplasms result in a disproportionate share of cancer morbidity and mortality. Treatment of HGG patients is directed not merely towards prolonging life but also towards quality of life, which becomes the major goal in the end of life

  13. Research design in end-of-life research: state of science.

    Science.gov (United States)

    George, Linda K

    2002-10-01

    The volume of research on end-of-life care, death, and dying has exploded during the past decade. This article reviews the conceptual and methodological adequacy of end-of-life research to date, focusing on limitations of research to date and ways of improving future research. A systematic search was conducted to identify the base of end-of-life research. Approximately 400 empirical articles were identified and are the basis of this review. Although much has been learned from research to date, limitations in the knowledge base are substantial. The most fundamental problems identified are conceptual and include failure to define dying; neglect of the distinctions among quality of life, quality of death, and quality of end-of-life care. Methodologically, the single greatest problem is the lack of longitudinal studies that cover more than the time period immediately before death. Gaps in the research base include insufficient attention to psychological and spiritual issues, the prevalence of psychiatric disorder and the effectiveness of the treatment of such disorders among dying persons, provider and health system variables, social and cultural diversity, and the effects of comorbidity on trajectories of dying.

  14. End of life care in sub-Saharan Africa: a systematic review of the qualitative literature

    NARCIS (Netherlands)

    Gysels, M.H.; Pell, C.; Straus, L.; Pool, R.

    2011-01-01

    Background End of life (EoL) care in sub-Saharan Africa still lacks the sound evidence-base needed for the development of effective, appropriate service provision. It is essential to make evidence from all types of research available alongside clinical and health service data, to ensure that EoL

  15. Culture and end of life care: a scoping exercise in seven European countries

    NARCIS (Netherlands)

    Gysels, M.; Evans, N.; Meñaca, A.; Andrew, E.; Toscani, F.; Finetti, S.; Pasman, H.R.; Higginson, I.; Harding, R.; Pool, R.

    2012-01-01

    Aim: Culture is becoming increasingly important in relation to end of life (EoL) care in a context of globalization, migration and European integration. We explore and compare socio-cultural issues that shape EoL care in seven European countries and critically appraise the existing research evidence

  16. Diversity in Defining End of Life Care: An Obstacle or the Way Forward?

    NARCIS (Netherlands)

    Gysels, M.; Evans, N.C.; Menaca, A.; Higginson, I.J.; Harding, R.; Pool, R.

    2013-01-01

    Aim:The terms used to describe care at the end of life (EoL), and its definitions, have evolved over time and reflect the changes in meaning the concept has undergone as the field develops. We explore the remit of EoL care as defined by experts in EoL care, from across Europe and beyond, to

  17. The End-of-Life Phase of High-Grade Glioma Patients: Dying With Dignity?

    NARCIS (Netherlands)

    Sizoo, E.M.; Taphoorn, M.J.B.; Uitdehaag, B.M.J.; Heimans, J.J.; Deliens, L.; Reijneveld, J.C.; Pasman, H.R.W.

    2013-01-01

    Background. In the end-of-life (EOL) phase, high-grade glioma (HGG) patients have a high symptom burden and often lose independence because of physical and cognitive dysfunction. This might affect the patient's personal dignity. We aimed to (a) assess the proportion of HGG patients dying with

  18. Symptoms and medication management in the end of life phase of high-grade glioma patients

    NARCIS (Netherlands)

    Koekkoek, J.A.F.; Dirven, L.; Sizoo, E.M.; Pasman, H.R.W.; Heimans, J.J.; Postma, T.J.; Deliens, L.; Grant, R.; McNamara, S.; Stockhammer, G.; Medicus, E.; Taphoorn, M.J.B.; Reijneveld, J.C.

    2014-01-01

    During the end of life (EOL) phase of high-grade glioma (HGG) patients, care is primarily aimed at reducing symptom burden while maintaining quality of life as long as possible. In this study, we evaluated the prevalence of symptoms and medication management in HGG patients during the EOL phase. We

  19. The new challenges of end-of-life tyres management systems: A Spanish case study

    Energy Technology Data Exchange (ETDEWEB)

    Uruburu, Ángel, E-mail: angel.uruburu@upm.es [Industrial Management Department, Technical University of Madrid, C/José Gutiérrez Abascal, 2, 28006 Madrid (Spain); Ponce-Cueto, Eva, E-mail: eva.ponce@upm.es [Industrial Management Department, Technical University of Madrid, C/José Gutiérrez Abascal, 2, 28006 Madrid (Spain); Center for Transportation and Logistics, Massachusetts Institute of Technology, Cambridge, MA (United States); Cobo-Benita, José Ramón, E-mail: joseramon.cobo@upm.es [Industrial Management Department, Technical University of Madrid, C/José Gutiérrez Abascal, 2, 28006 Madrid (Spain); Ordieres-Meré, Joaquín, E-mail: j.ordieres@upm.es [Industrial Management Department, Technical University of Madrid, C/José Gutiérrez Abascal, 2, 28006 Madrid (Spain)

    2013-03-15

    Highlights: ► Impact of the implementation of the Directive 2008/98/EC in Spain for end-of-life tyres. ► Characterization of the reverse supply chain for collecting, recovering, and treating end-of-life tyres. ► Identification of challenges to be coped and issues to be covered. ► Potential new applications for end-of-life tyres and development of new management related strategies. - Abstract: Directive 2008/98/EC released by the European Union represents a significant step forward in all relevant aspects of waste management. Under the already established, extended produced responsibility (EPR) principle, new policies have been enunciated to continuously achieve better overall environmental performance of key products throughout their life phases. This paper discusses how the directive is being articulated in Spain by the main integrated management system (IMS) for end-of-life (EOL) tyres since its creation in 2006. Focusing on the IMS technological, economic and legal aspects, the study provides a global perspective and evaluation of how the IMS is facing the current issues to resolve, the new challenges that have appeared and the management vision for the coming years.

  20. Culture and End of Life Care: A Scoping Exercise in Seven European Countries

    NARCIS (Netherlands)

    Gysels, M.; Evans, N.C.; Menaca, A.; Andrew, E.; Toscani, F.; Finetti, S.; Pasman, H.R.W.; Higginson, I.; Harding, R.; Pool, R.

    2012-01-01

    Aim: Culture is becoming increasingly important in relation to end of life (EoL) care in a context of globalization, migration and European integration. We explore and compare socio-cultural issues that shape EoL care in seven European countries and critically appraise the existing research evidence

  1. Diversity in defining end of life care: an obstacle or the way forward?

    NARCIS (Netherlands)

    Gysels, M.; Evans, N.; Meñaca, A.; Higginson, I.J.; Harding, R; Pool, R.

    2013-01-01

    Aim: The terms used to describe care at the end of life (EoL), and its definitions, have evolved over time and reflect the changes in meaning the concept has undergone as the field develops. We explore the remit of EoL care as defined by experts in EoL care, from across Europe and beyond, to

  2. Involvement of nurses in end-of-life discussions for severely disabled children

    NARCIS (Netherlands)

    Zaal-Schuller, I. H.; Willems, D. I.; Ewals, F.; van Goudoever, J. B.; de Vos, M. A.

    2018-01-01

    In children with profound intellectual and multiple disabilities (PIMD), discussions about end-of-life decisions (EoLDs) are comparatively common. Nurses play a crucial role in the care for these children, yet their involvement in EoLD discussions is largely unknown. The objective of this research

  3. Trends in End-of-Life Decision Making in Patients With and Without Cancer

    NARCIS (Netherlands)

    Pardon, K.; Chambaere, K.; Pasman, H.R.W.; Deschepper, R.; Rietjens, J.; Deliens, L.

    2013-01-01

    Purpose: Because of cancer's high symptom burden and specific disease course, patients with cancer are more likely than other patients to face end-of-life decisions that have possible or certain life-shortening effects (ELDs). This study examines the incidence of ELDs in patients with cancer

  4. End-of-life decision-making for children with severe developmental disabilities: The parental perspective

    NARCIS (Netherlands)

    Zaal-Schuller, I. H.; de Vos, M. A.; Ewals, F. V. P. M.; van Goudoever, J. B.; Willems, D. L.

    2016-01-01

    The objectives of this integrative review were to understand how parents of children with severe developmental disorders experience their involvement in end-of-life decision-making, how they prefer to be involved and what factors influence their decisions. We searched MEDLINE, EMBASE, CINAHL and

  5. End of Life Strategies Among Patients with Advanced Chronic Obstructive Pulmonary Disease (COPD).

    Science.gov (United States)

    Gershon, Andrea S; Maclagan, Laura C; Luo, Jin; To, Teresa; Kendzerska, Tetyana; Stanbrook, Matthew B; Bourbeau, Jean; Etches, Jacob; Aaron, Shawn D

    2018-06-11

    The burden of advanced COPD is high globally; however, little is known about how often end of life strategies are used by this population. To describe trends in the use of end of life care strategies by people with advanced COPD in Ontario, Canada. A population-based repeated cross-sectional study examining end of life care strategies in individuals with advanced COPD was conducted. Annual proportions of individuals who received formal palliative care, long-term oxygen therapy or opioids from 2004 to 2014 were determined. Results were age- and sex- standardized as well as stratified by age, sex, socioeconomic status, urban/rural residence and immigrant status. Measurement/Main Results: There were 151,912 persons with advanced COPD in Ontario between 2004 and 2014. Use of formal palliative care services increased 1% per year from 5.3% in 2004 to 14.3% in 2014 (p value for trend COPD using end of life strategies, although increasing, remains low. Efforts should focus on increasing access to such strategies as well as educating patients and providers of their benefits.

  6. The end-of-life phase of high-grade glioma patients: dying with dignity?

    NARCIS (Netherlands)

    Sizoo, Eefje M.; Taphoorn, Martin J. B.; Uitdehaag, Bernard; Heimans, Jan J.; Deliens, Luc; Reijneveld, Jaap C.; Pasman, H. Roeline W.

    2013-01-01

    In the end-of-life (EOL) phase, high-grade glioma (HGG) patients have a high symptom burden and often lose independence because of physical and cognitive dysfunction. This might affect the patient's personal dignity. We aimed to (a) assess the proportion of HGG patients dying with dignity as

  7. A preliminary categorization of end-of-life electrical and electronic equipment as secondary metal resources

    International Nuclear Information System (INIS)

    Oguchi, Masahiro; Murakami, Shinsuke; Sakanakura, Hirofumi; Kida, Akiko; Kameya, Takashi

    2011-01-01

    Highlights: → End-of-life electrical and electronic equipment (EEE) as secondary metal resources. → The content and the total amount of metals in specific equipment are both important. → We categorized 21 EEE types from contents and total amounts of various metals. → Important equipment types as secondary resources were listed for each metal kind. → Collectability and possible collection systems of various EEE types were discussed. - Abstract: End-of-life electrical and electronic equipment (EEE) has recently received attention as a secondary source of metals. This study examined characteristics of end-of-life EEE as secondary metal resources to consider efficient collection and metal recovery systems according to the specific metals and types of EEE. We constructed an analogy between natural resource development and metal recovery from end-of-life EEE and found that metal content and total annual amount of metal contained in each type of end-of-life EEE should be considered in secondary resource development, as well as the collectability of the end-of-life products. We then categorized 21 EEE types into five groups and discussed their potential as secondary metal resources. Refrigerators, washing machines, air conditioners, and CRT TVs were evaluated as the most important sources of common metals, and personal computers, mobile phones, and video games were evaluated as the most important sources of precious metals. Several types of small digital equipment were also identified as important sources of precious metals; however, mid-size information and communication technology (ICT) equipment (e.g., printers and fax machines) and audio/video equipment were shown to be more important as a source of a variety of less common metals. The physical collectability of each type of EEE was roughly characterized by unit size and number of end-of-life products generated annually. Current collection systems in Japan were examined and potentially appropriate collection

  8. Analysis of molten salt thermal-hydraulics using computational fluid dynamics

    International Nuclear Information System (INIS)

    Yamaji, B.; Csom, G.; Aszodi, A.

    2003-01-01

    To give a good solution for the problem of high level radioactive waste partitioning and transmutation is expected to be a pro missing option. Application of this technology also could extend the possibilities of nuclear energy. Large number of liquid-fuelled reactor concepts or accelerator driven subcritical systems was proposed as transmutors. Several of these consider fluoride based molten salts as the liquid fuel and coolant medium. The thermal-hydraulic behaviour of these systems is expected to be fundamentally different than the behaviour of widely used water-cooled reactors with solid fuel. Considering large flow domains three-dimensional thermal-hydraulic analysis is the method seeming to be applicable. Since the fuel is the coolant medium as well, one can expect a strong coupling between neutronics and thermal-hydraulics too. In the present paper the application of Computational Fluid Dynamics for three-dimensional thermal-hydraulics simulations of molten salt reactor concepts is introduced. In our past and recent works several calculations were carried out to investigate the capabilities of Computational Fluid Dynamics through the analysis of different molten salt reactor concepts. Homogenous single region molten salt reactor concept is studied and optimised. Another single region reactor concept is introduced also. This concept has internal heat exchanges in the flow domain and the molten salt is circulated by natural convection. The analysis of the MSRE experiment is also a part of our work since it may form a good background from the validation point of view. In the paper the results of the Computational Fluid Dynamics calculations with these concepts are presented. In the further work our objective is to investigate the thermal-hydraulics of the multi-region molten salt reactor (Authors)

  9. Methodology for thermal hydraulic conceptual design and performance analysis of KALIMER core

    International Nuclear Information System (INIS)

    Young-Gyun Kim; Won-Seok Kim; Young-Jin Kim; Chang-Kue Park

    2000-01-01

    This paper summarizes the methodology for thermal hydraulic conceptual design and performance analysis which is used for KALIMER core, especially the preliminary methodology for flow grouping and peak pin temperature calculation in detail. And the major technical results of the conceptual design for the KALIMER 98.03 core was shown and compared with those of KALIMER 97.07 design core. The KALIMER 98.03 design core is proved to be more optimized compared to the 97.07 design core. The number of flow groups are reduced from 16 to 11, and the equalized peak cladding midwall temperature from 654 deg. C to 628 deg. C. It was achieved from the nuclear and thermal hydraulic design optimization study, i.e. core power flattening and increase of radial blanket power fraction. Coolant flow distribution to the assemblies and core coolant/component temperatures should be determined in core thermal hydraulic analysis. Sodium flow is distributed to core assemblies with the overall goal of equalizing the peak cladding midwall temperatures for the peak temperature pin of each bundle, thus pin cladding damage accumulation and pin reliability. The flow grouping and the peak pin temperature calculation for the preliminary conceptual design is performed with the modules ORFCE-F60 and ORFCE-T60 respectively. The basic subchannel analysis will be performed with the SLTHEN code, and the detailed subchannel analysis will be done with the MATRA-LMR code which is under development for the K-Core system. This methodology was proved practical to KALIMER core thermal hydraulic design from the related benchmark calculation studies, and it is used to KALIMER core thermal hydraulic conceptual design. (author)

  10. Uncertainty Evaluation of the SFR Subchannel Thermal-Hydraulic Modeling Using a Hot Channel Factors Analysis

    International Nuclear Information System (INIS)

    Choi, Sun Rock; Cho, Chung Ho; Kim, Sang Ji

    2011-01-01

    In an SFR core analysis, a hot channel factors (HCF) method is most commonly used to evaluate uncertainty. It was employed to the early design such as the CRBRP and IFR. In other ways, the improved thermal design procedure (ITDP) is able to calculate the overall uncertainty based on the Root Sum Square technique and sensitivity analyses of each design parameters. The Monte Carlo method (MCM) is also employed to estimate the uncertainties. In this method, all the input uncertainties are randomly sampled according to their probability density functions and the resulting distribution for the output quantity is analyzed. Since an uncertainty analysis is basically calculated from the temperature distribution in a subassembly, the core thermal-hydraulic modeling greatly affects the resulting uncertainty. At KAERI, the SLTHEN and MATRA-LMR codes have been utilized to analyze the SFR core thermal-hydraulics. The SLTHEN (steady-state LMR core thermal hydraulics analysis code based on the ENERGY model) code is a modified version of the SUPERENERGY2 code, which conducts a multi-assembly, steady state calculation based on a simplified ENERGY model. The detailed subchannel analysis code MATRA-LMR (Multichannel Analyzer for Steady-State and Transients in Rod Arrays for Liquid Metal Reactors), an LMR version of MATRA, was also developed specifically for the SFR core thermal-hydraulic analysis. This paper describes comparative studies for core thermal-hydraulic models. The subchannel analysis and a hot channel factors based uncertainty evaluation system is established to estimate the core thermofluidic uncertainties using the MATRA-LMR code and the results are compared to those of the SLTHEN code

  11. Thermal-hydraulic analysis of SMART steam generator tube rupture using TASS/SMR-S code

    International Nuclear Information System (INIS)

    Kim, Hee-Kyung; Kim, Soo Hyoung; Chung, Young-Jong; Kim, Hyeon-Soo

    2013-01-01

    Highlights: ► The analysis was performed from the viewpoint of primary coolant leakage. ► The thermal hydraulic responses and the maximum leakage have been identified. ► There is no direct release into the atmosphere caused by an SGTR accident. ► SMART safety system works well against an SGTR accident. - Abstract: A steam generator tube rupture (SGTR) accident analysis for SMART was performed using the TASS/SMR-S code. SMART with a rated thermal power of 330 MWt has been developed at the Korea Atomic Energy Research Institute. The TASS/SMR-S code can analyze the thermal hydraulic phenomena of SMART in a full range of reactor operating conditions. An SGTR is one of the most important accidents from a thermal hydraulic and radiological viewpoint. A conservative analysis against a SMART SGTR was performed. The major concern of this analysis is to find the thermal hydraulic responses and maximum leakage amount from a primary to a secondary side caused by an SGTR accident. A sensitivity study searching for the conservative thermal hydraulic conditions, break locations, reactivity and other conditions was performed. The dominant parameters related with the integral leak are the high RCS pressure, low core inlet coolant temperature and low break location of the SG cassette. The largest integral leak comes to 28 tons in the most conservative case during 1 h. But there is no direct release into the atmosphere because the secondary system pressure is maintained with a sufficient margin for the design pressure. All leaks go to the condenser. The analysis results show that the primary and secondary system pressures are maintained below the design pressure and the SMART safety system is working well against an SGTR accident

  12. Patient-reported assessment of quality care at end of life: development and validation of Quality Care Questionnaire-End of Life (QCQ-EOL).

    Science.gov (United States)

    Yun, Young Ho; Kim, Soo-Hyun; Lee, Kyoung-Min; Park, Sang Min; Lee, Chang Geol; Choi, Youn Seon; Lee, Won Sup; Kim, Si-Young; Heo, Dae Seog

    2006-09-01

    Our goal was to validate an instrument with which terminally ill patients could evaluate the quality of care they receive at the end of life (EOL). Questionnaire development followed a four-phase process: item generation and reduction, construction, pilot testing, and field-testing. Using relevance and priority criteria and pilot testing, we developed a 16-item questionnaire. Factor analyses of data from 235 patients resulted in the Quality Care Questionnaire-End of Life (QCQ-EOL) covering dignity-conserving care, care by health care professionals, individualised care, and family relationships. All subscales and total scores showed high internal consistency (Cronbach alpha range, 0.73-0.89). The ability of total score and selective subscale scores clearly differentiated patients on the basis of clinical situation, sense of dignity, and general rating of care quality. Correlations of scores between patients and caregivers were substantial. The QCQ-EOL can be adopted to assess the quality of care received by terminally ill patients.

  13. Perspectives on spirituality at the end of life: a meta-summary.

    Science.gov (United States)

    Williams, Anna-Leila

    2006-12-01

    A meta-summary of the qualitative literature on spiritual perspectives of adults who are at the end of life was undertaken to summarily analyze the research to date and identify areas for future research on the relationship of spirituality with physical, functional, and psychosocial outcomes in the health care setting. Included were all English language reports from 1966 to the present catalogued in PubMed, Medline, PsycInfo, and CINAHL, identifiable as qualitative investigations of the spiritual perspectives of adults at the end of life. The final sample includes 11 articles, collectively representing data from 217 adults. The preponderance of participants had a diagnosis of cancer; those with HIV/AIDS, cardiovascular disease, and ALS were also represented. Approximately half the studies were conducted in the United States; others were performed in Australia, Finland, Scotland, and Taiwan. Following a process of theme extraction and abstraction, thematic patterns emerged and effect sizes were calculated. A spectrum of spirituality at the end of life encompassing spiritual despair (alienation, loss of self, dissonance), spiritual work (forgiveness, self-exploration, search for balance), and spiritual well-being (connection, self-actualization, consonance) emerged. The findings from this meta-summary confirm the fundamental importance of spirituality at the end of life and highlight the shifts in spiritual health that are possible when a terminally ill person is able to do the necessary spiritual work. Existing end-of-life frameworks neglect spiritual work and consequently may be deficient in guiding research. The area of spiritual work is fertile ground for further investigation, especially interventions aimed at improving spiritual health and general quality of life among the dying.

  14. End-of-life decisions for people with intellectual disabilities, an interview study with patient representatives.

    Science.gov (United States)

    Wagemans, Annemieke M A; Van Schrojenstein Lantman-de Valk, Henny M J; Proot, Ireen M; Metsemakers, Job; Tuffrey-Wijne, Irene; Curfs, Leopold M G

    2013-09-01

    Not much is known about the process of end-of-life decision-making for people with intellectual disabilities. To clarify the process of end-of-life decision-making for people with intellectual disabilities from the perspective of patient representatives. A qualitative study based on semi-structured interviews, recorded digitally and transcribed verbatim. Data were analysed using Grounded Theory procedures. We interviewed 16 patient representatives after the deaths of 10 people with intellectual disabilities in the Netherlands. The core category 'Deciding for someone else' describes the context in which patient representatives took end-of-life decisions. The patient representatives felt highly responsible for the outcomes. They had not involved the patients in the end-of-life decision-making process, nor any professionals other than the doctor. The categories of 'Motives' and 'Support' were connected to the core category of 'Deciding for someone else'. 'Motives' refers to the patient representatives' ideas about quality of life, prevention from suffering, patients who cannot understand the burden of interventions and emotional reasons reported by patient representatives. 'Support' refers to the support that patient representatives wanted the doctors to give to them in the decision-making process. From the perspective of the patient representatives, the process of end-of-life decision-making can be improved by ensuring clear roles and an explicit description of the tasks and responsibilities of all participants. Regular discussion between everyone involved including people with intellectual disabilities themselves can improve knowledge about each other's motives for end-of-decisions and can clarify expectations towards each other.

  15. Nurses' autonomy in end-of-life situations in intensive care units.

    Science.gov (United States)

    Paganini, Maria Cristina; Bousso, Regina Szylit

    2015-11-01

    The intensive care unit environment focuses on interventions and support therapies that prolong life. The exercise by nurses of their autonomy impacts on perception of the role they assume in the multidisciplinary team and on their function in the intensive care unit context. There is much international research relating to nurses' involvement in end-of-life situations; however, there is a paucity of research in this area in Brazil. In the Brazilian medical scenario, life support limitation generated a certain reluctance of a legal nature, which has now become unjustifiable with the publication of a resolution by the Federal Medical Council. In Brazil, the lack of medical commitments to end-of-life care is evident. To understand the process by which nurses exercise autonomy in making end-of-life decisions in intensive care units. Symbolic Interactionism and Corbin and Strauss theory methodology were used for this study. Data were collected through single audio-recorded qualitative interviews with 14 critical care nurses. The comparative analysis of the data has permitted the understanding of the meaning of nurse's experience in exercising autonomy relating to end-of-life decision-making. Institutional ethics approval was obtained for data collection. Participants gave informed consent. All data were anonymized. The results revealed that nurses experience the need to exercise autonomy in intensive care units on a daily basis. Their experience expressed by the process of increase opportunities to exercise autonomy is conditioned by the pressure of the intensive care unit environment, in which nurses can grow, feel empowered, and exercise their autonomy or else can continuously depend on the decisions made by other professionals. Nurses exercise their autonomy through care. They work to create new spaces at the same time that they acquire new knowledge and make decisions. Because of the complexity of the end-of-life situation, nurses must adopt a proactive attitude

  16. Perceived risks around choice and decision making at end-of-life: a literature review.

    Science.gov (United States)

    Wilson, F; Gott, M; Ingleton, C

    2013-01-01

    the World Health Organization identifies meeting patient choice for care as central to effective palliative care delivery. Little is known about how choice, which implies an objective balancing of options and risks, is understood and enacted through decision making at end-of-life. to explore how perceptions of 'risk' may inform decision-making processes at end-of-life. an integrative literature review was conducted between January and February 2010. Papers were reviewed using Hawker et al.'s criteria and evaluated according to clarity of methods, analysis and evidence of ethical consideration. All literature was retained as background data, but given the significant international heterogeneity the final analysis specifically focused on the UK context. the databases Medline, PsycINFO, Assia, British Nursing Index, High Wire Press and CINAHL were explored using the search terms decision*, risk, anxiety, hospice and palliative care, end-of-life care and publication date of 1998-2010. thematic analysis of 25 papers suggests that decision making at end-of-life is multifactorial, involving a balancing of risks related to caregiver support; service provider resources; health inequalities and access; challenges to information giving; and perceptions of self-identity. Overall there is a dissonance in understandings of choice and decision making between service providers and service users. the concept of risk acknowledges the factors that shape and constrain end-of-life choices. Recognition of perceived risks as a central factor in decision making would be of value in acknowledging and supporting meaningful decision making processes for patients with palliative care needs and their families.

  17. The role of the bioethicist in family meetings about end of life care.

    Science.gov (United States)

    Watkins, Liza T; Sacajiu, Galit; Karasz, Alison

    2007-12-01

    There has been little study of the content of bioethicists' communication during family meeting consultations about end of life care. In the literature, two roles for bioethicists are usually described: the "consultant" role, in which bioethicists define and support ethical principles such as those enshrined in the "rational choice" model; and the "mediator" role, which focuses on the enhancement of communication in order to reduce conflict. In this study, we use observational data to explore how bioethicists support the practice of decision making during family meetings about end of life care. In a study conducted in the Bronx, New York, USA, researchers observed and recorded 24 decision-making meetings between hospital staff and family members of elderly patients identified as being in the last stages of illness, who were unable or unwilling to make the decision for themselves. Bioethics consultants were present during five of those meetings. Although bioethicists referred to the "rational choice" decision-making hierarchy, we did not see the systematic exploration described in the literature. Rather, our data show that bioethicists tended to employ elements of the rational model at particular turning points in the decision-making process in order to achieve pragmatic goals. As mediators, bioethicists worked to create consensus between family and staff and provided invaluable sympathy and comfort to distressed family members. We also found evidence of a context-dependent approach to mediation, with bioethicists' contributions generally supporting staff views about end of life care. Bioethicists' called to consult on family meetings about end of life care do not appear to adhere to a strict interpretation of the official guidelines. In order to negotiate the difficult terrain of end of life decision making, our data show that bioethicists often add a third role, "persuader", to official roles of "consultant" and "mediator".

  18. Intensity of Care at the End of Life Among Older Adults in Korea.

    Science.gov (United States)

    Kim, Su Hyun; Kang, Sangwook; Song, Mi-Kyung

    2018-01-01

    To examine the intensity of care at the end of life among older adults in Korea and to identify the individual and institutional factors associated with care intensity. This secondary data analysis included a sample of 6278 decedents aged 65 years or older who were identified from the 2009 to 2010 Korean National Health Insurance Service-National Sample Cohort Claims data. We examined the medical care received by the cohort in the last 30 days of their lives. Overall, 36.5% of the sample received at least 1 intensive care procedure in the last 30 days of their lives; 26.3% of patients experienced intensive care unit admission, with an average stay of 7.45 days, 19.5% received mechanical ventilation, 12.3% received cardiopulmonary resuscitation, and 15.5% had a feeding tube placement. A statistical analysis using a multiple logistic regression model with random effects showed that younger age, higher household income, primary diagnoses of diseases (ischemic heart disease, infectious disease, chronic lung disease, or chronic heart disease), and characteristics of care setting (large hospitals and facilities located in metropolitan areas) were significantly associated with the likelihood of receiving high-intensity care at the end of life. A substantial number of older adults in Korea experienced high-intensity end-of-life care. Both individual and institutional factors were associated with the likelihood of receiving high-intensity care. Gaining an understanding of the intensity of care at the end of life and the impact of the determinants would advance efforts to improve quality of care at the end of life for older adults in Korea.

  19. Progress of the OODB study for PHENIX

    International Nuclear Information System (INIS)

    Ye Yanlin; Ying Jun; Xu Chuncheng; Chen Tao

    1997-01-01

    The background for developing Object-Oriented software technique in high-energy and nuclear physics has been outlined. The need for Object-oriented Database for PHENIX was analyzed. A prototype for PEP production control database is introduced

  20. Hospice family members’ perceptions and experiences with end-of-life care in the nursing home

    Science.gov (United States)

    Washington, Karla; Kruse, Robin L.; Albright, David L; Lewis, Alexandria; Demiris, George

    2014-01-01

    Objective Despite the fact that more than 25% of Americans die in nursing homes, end-of-life care has consistently been found to be less than adequate in this setting. Even for those residents on hospice, end-of-life care has been found to be problematic. This study had two research questions; 1) How do family members of hospice nursing home residents differ in their anxiety, depression, quality of life, social networks, perceptions of pain medication, and health compared to family members of community dwelling hospice patients? 2) What are family members’ perceptions of and experiences with end-of-life care in the nursing home setting? Methods This study is a secondary mixed methods analysis of interviews with family members of hospice nursing home residents and a comparative statistical analysis of standard outcome measures between family members of hospice patients in the nursing home and family member of hospice patients residing in the community. Results Outcome measures for family members of nursing home residents were compared (n=176) with family members of community dwelling hospice patients (n=267). The family members of nursing home residents reported higher quality of life however, levels of anxiety, depression, perceptions of pain medicine, and health were similar for hospice family members in the nursing home and in the community. Lending an understanding to the stress for hospice family members of nursing home residents concerns were found with collaboration between the nursing home and the hospice, nursing home care that did not meet family expectations, communication problems, and resident care concerns including pain management. Some family members reported positive end-of-life care experiences in the nursing home setting. Conclusion These interviews identify a multitude of barriers to quality end-of-life care in the nursing home setting, and demonstrate that support for family members is an essential part of quality end-of-life care for

  1. End-of-life conversations and care: an asset-based model for community engagement.

    Science.gov (United States)

    Matthiesen, Mary; Froggatt, Katherine; Owen, Elaine; Ashton, John R

    2014-09-01

    Public awareness work regarding palliative and end-of-life care is increasingly promoted within national strategies for palliative care. Different approaches to undertaking this work are being used, often based upon broader educational principles, but little is known about how to undertake such initiatives in a way that equally engages both the health and social care sector and the local communities. An asset-based community engagement approach has been developed that facilitates community-led awareness initiatives concerning end-of-life conversations and care by identifying and connecting existing skills and expertise. (1) To describe the processes and features of an asset-based community engagement approach that facilitates community-led awareness initiatives with a focus on end-of-life conversations and care; and (2) to identify key community-identified priorities for sustainable community engagement processes. An asset-based model of community engagement specific to end-of-life issues using a four-step process is described (getting started, coming together, action planning and implementation). The use of this approach, in two regional community engagement programmes, based across rural and urban communities in the northwest of England, is described. The assets identified in the facilitated community engagement process encompassed people's talents and skills, community groups and networks, government and non-government agencies, physical and economic assets and community values and stories. Five priority areas were addressed to ensure active community engagement work: information, outreach, education, leadership and sustainability. A facilitated, asset-based approach of community engagement for end-of-life conversations and care can catalyse community-led awareness initiatives. This occurs through the involvement of community and local health and social care organisations as co-creators of this change across multiple sectors in a sustainable way. This approach

  2. Typology of end-of-life priorities in Saudi females: averaging analysis and Q-methodology.

    Science.gov (United States)

    Hammami, Muhammad M; Hammami, Safa; Amer, Hala A; Khodr, Nesrine A

    2016-01-01

    Understanding culture-and sex-related end-of-life preferences is essential to provide quality end-of-life care. We have previously explored end-of-life choices in Saudi males and found important culture-related differences and that Q-methodology is useful in identifying intraculture, opinion-based groups. Here, we explore Saudi females' end-of-life choices. A volunteer sample of 68 females rank-ordered 47 opinion statements on end-of-life issues into a nine-category symmetrical distribution. The ranking scores of the statements were analyzed by averaging analysis and Q-methodology. The mean age of the females in the sample was 30.3 years (range, 19-55 years). Among them, 51% reported average religiosity, 78% reported very good health, 79% reported very good life quality, and 100% reported high-school education or more. The extreme five overall priorities were to be able to say the statement of faith, be at peace with God, die without having the body exposed, maintain dignity, and resolve all conflicts. The extreme five overall dis-priorities were to die in the hospital, die well dressed, be informed about impending death by family/friends rather than doctor, die at peak of life, and not know if one has a fatal illness. Q-methodology identified five opinion-based groups with qualitatively different characteristics: "physical and emotional privacy concerned, family caring" (younger, lower religiosity), "whole person" (higher religiosity), "pain and informational privacy concerned" (lower life quality), "decisional privacy concerned" (older, higher life quality), and "life quantity concerned, family dependent" (high life quality, low life satisfaction). Out of the extreme 14 priorities/dis-priorities for each group, 21%-50% were not represented among the extreme 20 priorities/dis-priorities for the entire sample. Consistent with the previously reported findings in Saudi males, transcendence and dying in the hospital were the extreme end-of-life priority and dis

  3. Typology of end-of-life priorities in Saudi females: averaging analysis and Q-methodology

    Science.gov (United States)

    Hammami, Muhammad M; Hammami, Safa; Amer, Hala A; Khodr, Nesrine A

    2016-01-01

    Background Understanding culture-and sex-related end-of-life preferences is essential to provide quality end-of-life care. We have previously explored end-of-life choices in Saudi males and found important culture-related differences and that Q-methodology is useful in identifying intraculture, opinion-based groups. Here, we explore Saudi females’ end-of-life choices. Methods A volunteer sample of 68 females rank-ordered 47 opinion statements on end-of-life issues into a nine-category symmetrical distribution. The ranking scores of the statements were analyzed by averaging analysis and Q-methodology. Results The mean age of the females in the sample was 30.3 years (range, 19–55 years). Among them, 51% reported average religiosity, 78% reported very good health, 79% reported very good life quality, and 100% reported high-school education or more. The extreme five overall priorities were to be able to say the statement of faith, be at peace with God, die without having the body exposed, maintain dignity, and resolve all conflicts. The extreme five overall dis-priorities were to die in the hospital, die well dressed, be informed about impending death by family/friends rather than doctor, die at peak of life, and not know if one has a fatal illness. Q-methodology identified five opinion-based groups with qualitatively different characteristics: “physical and emotional privacy concerned, family caring” (younger, lower religiosity), “whole person” (higher religiosity), “pain and informational privacy concerned” (lower life quality), “decisional privacy concerned” (older, higher life quality), and “life quantity concerned, family dependent” (high life quality, low life satisfaction). Out of the extreme 14 priorities/dis-priorities for each group, 21%–50% were not represented among the extreme 20 priorities/dis-priorities for the entire sample. Conclusion Consistent with the previously reported findings in Saudi males, transcendence and dying in

  4. Using motivational interviewing to facilitate death talk in end-of-life care: an ethical analysis.

    Science.gov (United States)

    Black, Isra; Helgason, Ásgeir Rúnar

    2018-03-21

    Morbidity arising from unprepared bereavement is a problem that affects close personal relations of individuals at the end-of-life. The bereavement studies literature demonstrates that a lack of preparedness for a loved one's death is a risk factor for secondary psychological morbidity among survivors. Short awareness time of death negatively correlates to preparedness for bereavement. The absence of disclosure of end-of-life diagnosis and prognosis to close personal relations ('death talk') between patients and loved ones, or health professionals and loved ones, may contribute to short awareness time of death. To increase awareness time of death, we might attempt to increase patient first-personal disclosure of end-of-life diagnosis and prognosis to loved-ones, and/or patient consent to health professional disclosure of the same. Interventions based on motivational interviewing in end-of-life care whose aim is to facilitate death talk, either by the patient directly, or by a health professional with the patient's consent, may offer a part solution to the problem of unprepared bereavement. This paper evaluates the ethical permissibility of such interventions. We consider two ethical objections to using motivational interviewing in this way: first, that it is inappropriate for practitioners to seek disclosure as an outcome in this setting; second, that aiming at disclosure risks manipulating individuals into death talk. While it need not be impermissible to direct individuals toward disclosure of end-of-life diagnosis/prognosis, the objection from manipulation implies that it is pro tanto ethically preferable to use motivational interviewing in a non-directive mode in death talk conversations. However, insofar as non-directive motivational interviewing requires more advanced skills, and thus may be more difficult to learn and to practise, we advance that it may be ethically permissible, all things considered, to employ directional, or specific outcome

  5. Proceedings of the ANS/ASME/NRC international topical meeting on nuclear reactor thermal-hydraulics: LMFBR and HTGR advanced reactor concepts and analysis methods

    International Nuclear Information System (INIS)

    1980-01-01

    Separate abstracts are included for each of the papers presented concerning the thermal-hydraulics of LMFBR type reactors; mathematical methods in nuclear reactor thermal-hydraulics; heat transfer in gas-cooled reactors; and thermal-hydraulics of pebble-bed reactors. Two papers have been previously abstracted and input to the data base

  6. Overview of the ANL advanced LMR system thermal-hydraulic test program supporting both GE/PRISM and RI/SAFR

    International Nuclear Information System (INIS)

    Oras, J.J.; Kuzay, T.M.; Kasza, K.E.

    1988-01-01

    Descriptions of the ANL thermal-hydraulic water models of both the PRISM and SAFR reactors are presented, together with results from Phases I and II of the thermal-hydraulic test program. Phenomena discovered during these tests and modeling results are presented. Overall, these efforts demonstrate the acceptable thermal-hydraulic performance of both the PRISM and SAFR concepts

  7. Whole core pin-by-pin coupled neutronic-thermal-hydraulic steady state and transient calculations using COBAYA3 code

    International Nuclear Information System (INIS)

    Jimenez, J.; Herrero, J. J.; Cuervo, D.; Aragones, J. M.

    2010-10-01

    Nowadays coupled 3-dimensional neutron kinetics and thermal-hydraulic core calculations are performed by applying a radial average channel approach using a meshing of one quarter of assembly in the best case. This approach does not take into account the subchannels effects due to the averaging of the physical fields and the loose of heterogeneity in the thermal-hydraulic model. Therefore the models do not have enough resolution to predict those subchannels effects which are important for the fuel design safety margins, because it is in the local scale, where we can search the hottest pellet or the maximum heat flux. The Polytechnic University of Madrid advanced multi-scale neutron-kinetics and thermal-hydraulics methodologies being implemented in COBAYA3 include domain decomposition by alternate core dissections for the local 3-dimensional fine-mesh scale problems (pin cells/subchannels) and an analytical nodal diffusion solver for the coarse mesh scale coupled with the thermal-hydraulic using a model of one channel per assembly or per quarter of assembly. In this work, we address the domain decomposition by the alternate core dissections methodology applied to solve coupled 3-dimensional neutronic-thermal-hydraulic problems at the fine-mesh scale. The neutronic-thermal-hydraulic coupling at the cell-subchannel scale allows the treatment of the effects of the detailed thermal-hydraulic feedbacks on cross-sections, thus resulting in better estimates of the local safety margins at the pin level. (Author)

  8. Parent Perspectives of Neonatal Intensive Care at the End-of-Life.

    Science.gov (United States)

    Currie, Erin R; Christian, Becky J; Hinds, Pamela S; Perna, Samuel J; Robinson, Cheryl; Day, Sara; Meneses, Karen

    2016-01-01

    This descriptive qualitative study explored parent experiences related to their infant's neonatal intensive care unit (NICU) hospitalization, end-of-life care, and palliative care consultation. "Life and death in the NICU environment" emerged as the primary theme with the following categories: ups and downs of parenting in the NICU, decision-making challenges in the NICU, and parent support. Parents encountered challenges with areas for improvement for end-of-life and palliative care in the NICU. Further research is necessary to understand barriers with integrating palliative care and curative care in the NICU, and how NICU care affects bereavement and coping outcomes after infant death. Copyright © 2016 Elsevier Inc. All rights reserved.

  9. Sedation, alimentation, hydration, and equivocation: careful conversation about care at the end of life.

    Science.gov (United States)

    Jansen, Lynn A; Sulmasy, Daniel P

    2002-06-04

    In the recent medical ethics literature, several authors have recommended terminal sedation and refusal of hydration and nutrition as important, morally acceptable, and relatively uncontroversial treatment options for end-of-life suffering. However, not all authors use these terms to refer to the same practices. This paper examines the various ways that the terms terminal sedation and refusal of hydration and nutrition have been used in the medical literature. Although some of these practices are ethically appropriate responses to end-of-life suffering, others (at least as they are currently described in the medical ethics literature) are not. This paper identifies and discusses the principles that morally distinguish these practices from one another and specifically describes different features of medical practices and moral principles that affect the moral acceptability of various medical treatments. These distinctions reveal the complexity of the issues surrounding terminal sedation and refusal of hydration and nutrition, a complexity that has not been adequately addressed in recent discussions.

  10. Evaluating a Clinical Decision Support Interface for End-of-Life Nurse Care.

    Science.gov (United States)

    Febretti, Alessandro; Stifter, Janet; Keenan, Gail M; Lopez, Karen D; Johnson, Andrew; Wilkie, Diana J

    2014-01-01

    Clinical Decision Support Systems (CDSS) are tools that assist healthcare personnel in the decision-making process for patient care. Although CDSSs have been successfully deployed in the clinical setting to assist physicians, few CDSS have been targeted at professional nurses, the largest group of health providers. We present our experience in designing and testing a CDSS interface embedded within a nurse care planning and documentation tool. We developed four prototypes based on different CDSS feature designs, and tested them in simulated end-of-life patient handoff sessions with a group of 40 nurse clinicians. We show how our prototypes directed nurses towards an optimal care decision that was rarely performed in unassisted practice. We also discuss the effect of CDSS layout and interface navigation in a nurse's acceptance of suggested actions. These findings provide insights into effective nursing CDSS design that are generalizable to care scenarios different than end-of-life.

  11. Hypnosis for Symptom Control in Cancer Patients at the End-of-Life: A Systematic Review.

    Science.gov (United States)

    Montgomery, Guy H; Sucala, Madalina; Baum, Tessa; Schnur, Julie B

    2017-01-01

    Hypnosis has been shown to alleviate symptoms and side effects of cancer and its treatment. However, less is known about the use of hypnosis at the end of life in individuals with cancer. Our goal was to systematically review the literature on the use of hypnosis to manage the most common symptoms of end-of-life cancer patients: fatigue, sleep disturbances, pain, appetite loss, and dyspnea. EMBASE, MEDLINE, COCHRANE, PsychINFO, and SCOPUS databases were searched from inception through November 7, 2016. No studies met the inclusion criteria. It appears that hypnosis has never been rigorously tested as a means to ameliorate the most common symptoms in individuals with cancer at the end of their lives. This finding is troubling, as it strongly implies that a population most in need has been largely neglected. However, a clear future research direction is revealed that may have significant clinical impact.

  12. Typology of end-of-life priorities in Saudi females: averaging analysis and Q-methodology

    Directory of Open Access Journals (Sweden)

    Hammami MM

    2016-05-01

    Full Text Available Muhammad M Hammami,1,2 Safa Hammami,1 Hala A Amer,1 Nesrine A Khodr1 1Clinical Studies and Empirical Ethics Department, King Faisal Specialist Hospital and Research Centre, 2College of Medicine, Alfaisal University, Riyadh, Saudi Arabia Background: Understanding culture-and sex-related end-of-life preferences is essential to provide quality end-of-life care. We have previously explored end-of-life choices in Saudi males and found important culture-related differences and that Q-methodology is useful in identifying intraculture, opinion-based groups. Here, we explore Saudi females’ end-of-life choices.Methods: A volunteer sample of 68 females rank-ordered 47 opinion statements on end-of-life issues into a nine-category symmetrical distribution. The ranking scores of the statements were analyzed by averaging analysis and Q-methodology.Results: The mean age of the females in the sample was 30.3 years (range, 19–55 years. Among them, 51% reported average religiosity, 78% reported very good health, 79% reported very good life quality, and 100% reported high-school education or more. The extreme five overall priorities were to be able to say the statement of faith, be at peace with God, die without having the body exposed, maintain dignity, and resolve all conflicts. The extreme five overall dis-priorities were to die in the hospital, die well dressed, be informed about impending death by family/friends rather than doctor, die at peak of life, and not know if one has a fatal illness. Q-methodology identified five opinion-based groups with qualitatively different characteristics: “physical and emotional privacy concerned, family caring” (younger, lower religiosity, “whole person” (higher religiosity, “pain and informational privacy concerned” (lower life quality, “decisional privacy concerned” (older, higher life quality, and “life quantity concerned, family dependent” (high life quality, low life satisfaction. Out of the

  13. Identifying care actions to conserve dignity in end-of-life care.

    Science.gov (United States)

    Brown, Hilary; Johnston, Bridget; Ostlund, Ulrika

    2011-05-01

    Community nurses have a central role in the provision of palliative and end-of-life care; helping people to die with dignity is an important component of this care. To conserve dignity, care should comprise a broad range of actions addressing the distress that might impact on the patient's sense of dignity. These care actions need to be defined. This study aims to suggest care actions that conserve dignity at the end of life based on evidence from local experience and community nursing practice. Data were collected by focus group interviews and analysed by framework analysis using the Chochinov model of dignity as a predefined framework. Suggestions on care actions were given in relation to all themes. As part of a multi-phase project developing and testing a dignity care pathway, this study might help community nurses to conserve dying patients' dignity.

  14. [End-of-life-care and euthanasia: medical assistance in dying or help to die].

    Science.gov (United States)

    Müller-Busch, H Christof

    2008-01-01

    The debate on euthanasia that has been started all over Europe, but especially in Germany has been particularly complicated by unclear and inconsistent definitions. Medical decisions in end-of-life care gain increasing importance not only for the time of death but also for the kind and quality of the dying process. Though legal regulations can help to diminish doubts about the permissibility of various measures in end-of-life care, teaching and knowledge of ethical principles, communication skills, respect, transparency and knowledge of palliative care options seem to be the most important factors in accompanying the dying professionally and with dignity and even in achieving a consented compromise when aid in hastening death is asked for.

  15. The rational choice model in family decision making at the end of life.

    Science.gov (United States)

    Karasz, Alison; Sacajiu, Galit; Kogan, Misha; Watkins, Liza

    2010-01-01

    Most end-of-life decisions are made by family members. Current ethical guidelines for family decision making are based on a hierarchical model that emphasizes the patient's wishes over his or her best interests. Evidence suggests that the model poorly reflects the strategies and priorities of many families. Researchers observed and recorded 26 decision-making meetings between hospital staff and family members. Semi-structured follow-up interviews were conducted. Transcriptions were analyzed using qualitative techniques. For both staff and families, consideration of a patient's best interests generally took priority over the patient's wishes. Staff generally introduced discussion of the patient's wishes for rhetorical purposes, such as persuasion. Competing moral frameworks, which de-emphasized the salience of patients' autonomy and "right to choose," played a role in family decision making. The priority given to the patients' wishes in the hierarchical model does not reflect the priorities of staff and families in making decisions about end-of-life care.

  16. Continuous subcutaneous levetiracetam in the management of seizures at the end of life: a case report.

    Science.gov (United States)

    Wells, Geoffrey Howard; Mason, Louise D; Foreman, Emma; Chambers, John

    2016-03-01

    We report the case of a man who developed seizures on a background of recurrent metastatic squamous cell carcinoma with intracranial involvement. Initial seizure control with enteral levetiracetam was achieved, and when enteral and intravenous (i.v.) access was no longer available, a continuous subcutaneous infusion (CSCI) of levetiracetam successfully controlled his seizures without the need for sedating anticonvulsants. As a result, end-of-life care was able to be given with the patient retaining the ability to communicate with his family and healthcare staff. This report adds to the sparse but growing evidence base for the use of subcutaneous levetiracetam to manage seizures in palliative and end-of-life care. © The Author 2016. Published by Oxford University Press on behalf of the British Geriatrics Society. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

  17. Patients' perspective on deactivation of the implantable cardioverter-defibrillator near the end of life

    DEFF Research Database (Denmark)

    Pedersen, Susanne S.; Chaitsing, Rismy; Szili-Torok, Tamas

    2013-01-01

    (67%) completed the survey. Most patients (68%) were aware that it is possible to turn the ICD off, and 95% believed it is important to inform patients about the possibility. Of the patients completing the survey, 84% indicated a choice for or against deactivation. Psychological morbidity......Recent guidelines have emphasized the importance of discussing the issue of deactivation near the end of life with patients with an implantable cardioverter-defibrillator (ICD). Few studies have examined the patient perspective and patients' wishes. We examined patients' knowledge and wishes...... for information; and the prevalence and correlates of a favorable attitude toward deactivation. Three cohorts of ICD patients (n = 440) extracted from our institutional database were asked to complete a survey that included a vignette about deactivation near the end of life. Of the 440 patients approached, 294...

  18. The 'French exception': the right to continuous deep sedation at the end of life.

    Science.gov (United States)

    Horn, Ruth

    2018-03-01

    In 2016, a law came into force in France granting terminally ill patients the right to continuous deep sedation (CDS) until death. This right was proposed as an alternative to euthanasia and presented as the 'French response' to problems at the end of life. The law draws a distinction between CDS and euthanasia and other forms of sympton control at the end of life. France is the first country in the world to legislate on CDS . This short report describes the particular context and underlying social values that led to this piece of legislation, and explores its meaning in the wider French context. © Article author(s) (or their employer(s) unless otherwise stated in the text of the article) 2018. All rights reserved. No commercial use is permitted unless otherwise expressly granted.

  19. The end of life decisions -- should physicians aid their patients in dying?

    Science.gov (United States)

    Sharma, B R

    2004-06-01

    Decisions pertaining to end of life whether legalized or otherwise, are made in many parts of the world but not reported on account of legal implications. The highly charged debate over voluntary euthanasia and physician assisted suicide was brought into the public arena again when two British doctors confessed to giving lethal doses of drugs to hasten the death of terminally ill patients. Lack of awareness regarding the distinction between different procedures on account of legal status granted to them in some countries is the other area of concern. Some equate withdrawal of life support measures to physician assisted suicide whereas physician assisted suicide is often misinterpreted as euthanasia. Debate among the medical practitioners, law makers and the public taking into consideration the cultural, social and religious ethos will lead to increased awareness, more safeguards and improvement of medical decisions concerning the end of life. International Human Rights Law can provide a consensual basis for such a debate on euthanasia.

  20. Rethinking Suffering: Allowing for Suffering that is Intrinsic at End of Life.

    Science.gov (United States)

    Rattner, Maxxine; Berzoff, Joan

    2016-01-01

    The dilemma so central to the work of providers of palliative and end-of-life care is the paradox of their professional and ethical duty to try to relieve suffering and the limitations of so doing. While the capacity to sit with suffering at the end of life is critical to clinical work, the idea that some intrinsic suffering cannot necessarily always be relieved may model for patients and families that suffering can be borne. Clinicians who encounter unrelievable suffering may feel a sense of failure, helplessness, moral distress, and compassion fatigue. While tolerating suffering runs counter to the aims of palliative care, acknowledging it, bearing it, and validating it may actually help patients and families to do the same. "Sitting with suffering" signals a paradigm shift within the discipline of palliative care, as it asks clinicians to rethink their role in being able to relieve some forms of psychosocial suffering intrinsic to dying.