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Progress report on research and development in 1991, Institute of Reactor Development, KfK; Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1991, Institut fuer Reaktorentwicklung, KfK

Abstract

Progress report on research and development in 1991 Institute of Reactor Development. The papers on nuclear fusion concentrate on the design and material selection for highly stressed components as well as on safety matters. Experiments with the thermomechanical behaviour of different material samples continued, with selected materials being put to a load of up to 10 000 cycles. Carbon fiber reinforced composite materials proved to be very stable as regards their form, and unproblematic from a thermomechanical viewpoint, even at high cycle numbers. The papers on handling techniques refer to specific requirements of nuclear fusion with applications at JET and NET, to the development of system solutions to be used in the classical industrial area, and to standardization accompanying the developments. The system for physical simulation of working scenes was refined and extended by models for the prototype of a testing device to be handled in the torus of a fusion machine. Control of the articulated boom has been further improved. Under the nuclear safety research project, studies have been made of the dynamic behaviour of fast reactors under incident conditions, of the possible propagation of local cooling incidents in the reactor core as well as of core monitoring. The  More>>
Publication Date:
Mar 01, 1992
Product Type:
Technical Report
Report Number:
KFK-5037
Reference Number:
SCA: 220900; 210200; 210300; 420205; PA: DEN-93:002315; SN: 93000952943
Resource Relation:
Other Information: PBD: Mar 1992
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; REACTOR COMPONENTS; NET TOKAMAK; ITER TOKAMAK; REACTOR SAFETY; LMFBR TYPE REACTORS; PWR TYPE REACTORS; REMOTE HANDLING EQUIPMENT; REACTOR ACCIDENTS; AFTER-HEAT REMOVAL; MELTDOWN; RESEARCH PROGRAMS; PROGRESS REPORT; 220900; 210200; 210300; 420205; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; POWER REACTORS, NONBREEDING, GRAPHITE MODERATED; TRANSPORT AND STORAGE FACILITIES
OSTI ID:
10132473
Research Organizations:
Kernforschungszentrum Karlsruhe GmbH (Germany). Inst. fuer Reaktorentwicklung (IRE)
Country of Origin:
Germany
Language:
German
Other Identifying Numbers:
Other: ON: DE93771663; TRN: DE9302315
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
DEN
Size:
28 p.
Announcement Date:
Jul 04, 2005

Citation Formats

None. Progress report on research and development in 1991, Institute of Reactor Development, KfK; Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1991, Institut fuer Reaktorentwicklung, KfK. Germany: N. p., 1992. Web.
None. Progress report on research and development in 1991, Institute of Reactor Development, KfK; Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1991, Institut fuer Reaktorentwicklung, KfK. Germany.
None. 1992. "Progress report on research and development in 1991, Institute of Reactor Development, KfK; Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1991, Institut fuer Reaktorentwicklung, KfK." Germany.
@misc{etde_10132473,
title = {Progress report on research and development in 1991, Institute of Reactor Development, KfK; Ergebnisbericht ueber Forschungs- und Entwicklungsarbeiten 1991, Institut fuer Reaktorentwicklung, KfK}
author = {None}
abstractNote = {Progress report on research and development in 1991 Institute of Reactor Development. The papers on nuclear fusion concentrate on the design and material selection for highly stressed components as well as on safety matters. Experiments with the thermomechanical behaviour of different material samples continued, with selected materials being put to a load of up to 10 000 cycles. Carbon fiber reinforced composite materials proved to be very stable as regards their form, and unproblematic from a thermomechanical viewpoint, even at high cycle numbers. The papers on handling techniques refer to specific requirements of nuclear fusion with applications at JET and NET, to the development of system solutions to be used in the classical industrial area, and to standardization accompanying the developments. The system for physical simulation of working scenes was refined and extended by models for the prototype of a testing device to be handled in the torus of a fusion machine. Control of the articulated boom has been further improved. Under the nuclear safety research project, studies have been made of the dynamic behaviour of fast reactors under incident conditions, of the possible propagation of local cooling incidents in the reactor core as well as of core monitoring. The further development of physical models and computer programs on the dynamic behaviour of fast sodium-cooled reactors has been supported by experimental results. (orig./DG). [Deutsch] Die Beitraege zur Kernfusion konzentrieren sich auf den Entwurf und die Werkstoffauswahl fuer hochbelastete Komponenten sowie auf Sicherheitsfragen. Die Versuche zum thermomechanischen Verhalten unterschiedlicher Werkstoffproben wurden fortgesetzt, wobei ausgewaehlte Werkstoffe mit bis zu 10 000 Zyklen belastet wurden. Kohlenstoffaserverstaerkte Verbundwerkstoffe haben sich dabei auch bei hohen Zykluszahlen als sehr formstabil und aus thermomechanischer Sicht unproblematisch erwiesen. Die Beitraege zur Handhabungstechnik beziehen sich auf spezifische Anforderungen der Kernfusion mit Anwendungen bei JET und NET, auf die Entwicklung von Systemloesungen zur Anwendung im klassischen industriellen Bereich sowie auf die entwicklungsbegleitende Normung. Das System zur raeumlichen Simulation der Arbeitsszenen wurde verfeinert und durch Modelle fuer den Prototyp der Versuchseinrichtung zur Handhabung im Torus einer Fusionsmaschine erweitert. Die Steuerung des Vielgelenkmasts wurde weiter verbessert. Fuer das Projekt Nukleare Sicherheitsforschung laufen Untersuchungen zum dynamischen Verhalten schneller Reaktoren unter Stoerfallbedingungen, zur moeglichen Ausbreitung lokaler Kuehlungsstoerungen im Reaktorkern sowie zur Kernueberwachung. Die Weiterentwicklung von physikalischen Modellen und Rechenprogrammen zum dynamischen Verhalten schneller natriumgekuehlter Reaktoren wird durch experimentelle Ergebnisse gestuetzt. (orig./DG).}
place = {Germany}
year = {1992}
month = {Mar}
}