Search

BACKGROUND AND OBJECTIVE: Little is known about how experience with a previous acute myocardial infarction (AMI) impacts individuals' reactions to symptoms of a recurrent episode. Thus, the purpose of this study was to compare the use of coping strategies during an acute cardiac event in patients experiencing a first AMI with those experiencing a recurrent AMI. SUBJECTS AND METHODS: Secondary data analyses were performed to examine differences in the use of coping strategies between individuals with and without a history of AMI. Mann-Whitney U test was performed to compare those with (n = 26) and without (n = 109) a previous AMI with respect to 15 coping strategies, each of which was measured on a 5-point Likert scale. RESULTS AND CONCLUSIONS: Patients with a history of AMI were more likely to use prescribed medications to deal with their symptoms than were patients who did not have a previous AMI (M = 1.5 and 0.20; median = 2.0 and 0.0, respectively; P < .001). However, patients who had no previous AMI were more likely to respond by taking nonprescription medications (M = 0.90 and 0.60; median = 1.0 and 0.0, respectively; P = .04). The results suggest that patients with and without a history of AMI tend to respond to their symptoms with similar coping strategies. When differences occurred, patients with and without a history of AMI differed only with respect to the type of self-medication choices they made. Implications pertaining to these findings are discussed.

BACKGROUND AND OBJECTIVE: Little is known about how experience with a previous acute myocardial infarction (AMI) impacts individuals' reactions to symptoms of a recurrent episode. Thus, the purpose of this study was to compare the use of coping strategies during an acute cardiac event in patients experiencing a first AMI with those experiencing a recurrent AMI. SUBJECTS AND METHODS: Secondary data analyses were performed to examine differences in the use of coping strategies between individuals with and without a history of AMI. Mann-Whitney U test was performed to compare those with (n = 26) and without (n = 109) a previous AMI with respect to 15 coping strategies, each of which was measured on a 5-point Likert scale. RESULTS AND CONCLUSIONS: Patients with a history of AMI were more likely to use prescribed medications to deal with their symptoms than were patients who did not have a previous AMI (M = 1.5 and 0.20; median = 2.0 and 0.0, respectively; P < .001). However, patients who had no previous AMI were more likely to respond by taking nonprescription medications (M = 0.90 and 0.60; median = 1.0 and 0.0, respectively; P = .04). The results suggest that patients with and without a history of AMI tend to respond to their symptoms with similar coping strategies. When differences occurred, patients with and without a history of AMI differed only with respect to the type of self-medication choices they made. Implications pertaining to these findings are discussed. © 2007 Lippincott Williams & Wilkins, Inc.

The modular computer code FRESCO has been developed to describe the mechanism of fission product release from a HTGR-Core under accident conditions. By changing some program modules it has been exterided to take into account the transport phenomena (i.e. recoil) too, which only occur under reactor operating conditions and during the irradiation experiments. For this report, the release of cesium and strontium from three HTGR-fuel elements has been evaluated and compared with the experimental data. The results show that the measured release can be described by the considered models.

Im Frühjahr 1982 stellte die Kernforschungsanlage (KFA) Jülich in einem zusammenfassenden Bericht /l/ das Konzept einer nuklearen Prozeßwärmeanlage vor. Die Anlage mit einem Kugel häufen-HTR von 50 MW$_{th}$, als Wärmequelle erhielt in Anlehnung an den seit 1967 mit Erfolg auf dem Gelände der KFA betriebenenHTR die Bezeichnung AVR II. Im Rahmen der Konzeptentwicklung lag die Federführung für die Entwicklung des Sicherheitskonzeptes und für die Durchführung der Sicherheitsanalysen beim Institut für Nukleare Sicherheitsforschung (ISF). Das ISF wurde bei dieser Aufgabe von anderen KFA-Instituten - insbesondere dem Institut für Reaktorentwicklung (IRE) und dem Institut für Reaktorbauelemente (IRB) - unterstützt. Aus Platzgründen sind im Sicherheitskapitel des Konzeptberichtes nur die wesentlichen Ergebnisse dieser Arbeiten wiedergegeben. Es bestand daher der Wunsch, alle sicherheitstechnischen Arbeiten in einem gesonderten Bericht umfassend darzustellen und nachprüfbar zu dokumentieren, zumal viele Arbeiten auch für die an anderer Stelle laufende Entwicklung eines Modul-HTR von Bedeutungsind. Dies ist der Zweck des vorliegenden Berichtes. Er enthält in einer Sammlung von Einzelbeiträgen alle sicherheitsrelevanten Untersuchungen, die vom ISF im Rahmen der Konzeptentwicklung des AVR II durchgeführt wurden. Die Sammlung ist vollständig bis auf die thermodynamisehen Untersuchungen zum Nachweis der Wirksamkeit der Nachwärmeabfuhr bei Ausfall der Zwangskühlung und die Abschätzung der spontanen Aktivitätsfreisetzung aus dem Primärkreislauf bei Bruch der Primärkreisumschließung. Diese Arbeiten sind im IRE bzw. IRB durchgeführt worden. In sicherheitstechnischer Hinsicht unterscheidet sich der AVR II wesentlich von den bislang hauptsächlich untersuchten größeren Anlagen mit thermischen Leistungen von vielen hundert Megawatt. Hauptunterschiede sind: - schlanker Stahldruckbehälter statt Spannbetonbehälter, - kein separates Nachwärmeabfuhrsystem, - Nachwärmeabfuhr über die Oberfläche des Stahldruckbehälters möglich,- Steuerung und Abschaltung nur über Reflektorstäbe, - geringe Redundanz der Betriebssysteme, - vereinfachtes Containment, - Flächenkühler zur Kühlung der Reaktorkaverne. Die Sicherheit beruht im wesentlichen auf passiven Systemeigenschaften; dadurch können die Anforderungen an aktive Sicherheitseinrichtungen reduziert [...]

This report presents an analysis of the consequences for the High Temperature Reactor PNP-500 which occur during core cooling accidents. The consequences of the temperature transients and the fission product behaviour are considered for the primary circuit. The analysis shows that, even for an extremely delayed start of the afterheat removal system, the retention of caesium in the graphite of the fuel elements and of the bottom reflector reduces the release of the coated particles by more than two orders of magnitude. The plate out in the steam generator leads temporarily to a further, however, much smaller retention of the release flow.