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AbstractAbstract
[en] In case of a single phase gas cooled reactor (GCR), the DNBR is not of concern. Integrity of the other components such as the pressure vessel, the pipes, the pump, and the steam generator are considered the same as a fossil power plant as well as a LWR. Nuclear graphite blocks in GCR are known to have much higher resistance to thermal transients than metallic alloys so that its integrity is considered maintained. It is also known that the thermal shock resistance of TRISO fuel particle is very high so that the load follow capability of a HTGR is excellent. However, we were not able to find a quantitative analysis on the thermal shock resistance of TRISO particle. There are numerous computer models to describe TRISO fuel performance during a steady state irradiation such as COPA. Since those are lacking the short time transient calculation capabilities, we have developed a new computer model and used it to simulate the stress behavior of a TRISO particle during transient including extreme one as well as load follow operation in this study. TRISO is strongly resistant against thermal transient. Thus there should be no practical limit on fuel for the load following operation. Further calculations shows that, additional graphite layer of few milli-meter is sufficient to ensure the thermal resistance under extreme quench
Primary Subject
Secondary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; Oct 2013; [2 p.]; 2013 Fall meeting of the KNS; Kyungju (Korea, Republic of); 23-25 Oct 2013; Available from KNS, Daejeon (KR); 11 refs, 3 figs
Record Type
Miscellaneous
Literature Type
Conference
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Scott, J.L.
Oak Ridge National Lab., Tenn. (USA)1975
Oak Ridge National Lab., Tenn. (USA)1975
AbstractAbstract
[en] Research and development programs from 1945 to the present on coated-particle fuels are reviewed. 11 references. (U.S.)
Primary Subject
Source
1975; 7 p; American Nuclear Society meeting; New Orleans, Louisiana, USA; 8 Jun 1975
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
Reference NumberReference Number
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INIS IssueINIS Issue
Kofler, O.
Oesterreichische Studiengesellschaft fuer Atomenergie G.m.b.H., Vienna1980
Oesterreichische Studiengesellschaft fuer Atomenergie G.m.b.H., Vienna1980
AbstractAbstract
[en] Description of method and handling of fluidized beds with variable velocity of gas. Special use for coating fuel particles of reactors. (J.K.)
Original Title
Verfahren und Vorrichtung zum Betrieb einer Wirbelschicht
Primary Subject
Secondary Subject
Source
15 Apr 1980; 7 p; AT PATENT DOCUMENT 359613/B/; Available from the Oesterreichisches Patentamt, Kohlmarkt 8-10, A-1010 Vienna, Austria
Record Type
Patent
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Patent
Primary Subject
Source
2 Jul 1974; 6 p; US PATENT DOCUMENT 3,822,140
Record Type
Patent
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
No abstract available
Original Title
Der gasgekuehlte Brutreaktor mit Coated-Particle Brennelement und dessen Coreoptimierung
Primary Subject
Source
Deutsches Atomforum e.V., Bonn (F.R. Germany); p. 720-723; 1972; ZAED; Leopoldshafen, F.R. Germany; Reactor meeting; Hamburg, F.R. Germany; 11 Apr 1972; 1 tab.; 2 refs.; with figs. Short communication only.
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Felt, R.E.
Exxon Nuclear Co., Inc., Richland, WA (USA)1980
Exxon Nuclear Co., Inc., Richland, WA (USA)1980
AbstractAbstract
[en] Development of processes by Exxon Nuclear Company, Inc. for fabricating spherical particle nuclear fuel (sphere-pac) during October 1979 through March 1980 is reported. The program surveyed available technology to develop an initial flowsheet as a design basis for process development. An 0.1 ton/day pilot plant was built to develop and demonstrate the fabrication of sphere-pac fuel. Process and equipment efforts have been directed towards the demonstration of processes and equipment necessary to fabricate sphere-pac fuel on a commercial scale
Primary Subject
Source
May 1980; 39 p; Available from NTIS., PC A03/MF A01
Record Type
Report
Literature Type
Progress Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Kim, Woong Ki; Park, J. Y.; Kim, W. J.; Kim, Y. M.; Jeong, K. C.; Kim, Y. K.; Oh, S. C.; Lee, Y. W.; Cho, M. S.
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2008
Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)2008
AbstractAbstract
[en] The coated particle for the PYCASSO program is composed of zirconia kernel with a diameter of 0.5 mm and a PyC(pyrolytic carbon) coating layer with a thickness of 0.1 mm to produce physical data of PyC layer under the neutron irradiation in a reactor. TR126(1.06 g/cm3), TR127(1.76 g/cm3), TR131(1.95 g/cm3) and TR133(2.07 g/cm3) samples were prepared to analyze the effect of the variation of PyC layer density. The optical anisotropy factor(OPTAF) of PyC layer was measured by analyzing the polarization characteristics of the reflected light on the surface of a sample by using a photometer composed of a polarization microscope, data processor, a light source and a detector. The OPTAF of PyC layer for the samples ranged from 1.04 to 1.05. The OPTAF could be transformed into BAF(Bacon anisotropy factor) in the range of 1.14 to 1.16
Primary Subject
Source
Jan 2008; 56 p; Also available from KAERI; 7 refs, 48 figs, 46 tabs
Record Type
Report
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Country of publication
Reference NumberReference Number
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AbstractAbstract
No abstract available
Primary Subject
Record Type
Journal Article
Literature Type
Progress Report
Journal
Nuclear Science and Engineering; v. 44 p. 12-17
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Barthels, H.; Fassbender, J.; Katscher, W.
Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.); Deutsches Patentamt, Muenchen (Germany, F.R.)1978
AbstractAbstract
[en] The fuel body of a fuel element consists of fuel particles coated with pyrolytic carbon arranged between walls constructed as screens. The screens are formed as cones, double cones or as corrugated pipes and move between the pipe walls of the cylindrical fuel element from one side to the other and back. The particles are held in their position by graphite-felt, graphite fabric or felt or fabric made of SiO2. This stable geometric configuration guarantees that during operation changes of the power distribution in the reactor and reactivity jumps can be avoided. In research reactors even the emergency cooling becomes easier to be carried out. (orig.)
[de]
Bei dem BE ist der Brennstoffkoerper aus mit pyrolytischem Kohlenstoff beschichteten Partikeln zwischen als Siebe ausgebildeten Wandungen angeordnet. Die Siebe verlaufen kegel-, doppelkegel- oder wellrohrfoermig zwischen den Rohrwaenden des hohlzylinderfoermigen BE hin und her. Die Partikel werden ausserdem durch die Einlagerung von Graphitfilz, Graphitgewebe bzw. Gewebe und Filz aus SiO2 in unveraenderlicher Lage gehalten. Diese stabile geometrische Konfiguration gewaehrleistet, dass Aenderungen der Leistungsverteilung im Reaktor waehrend des Betriebs sowie Reaktivitaetsspruenge vermieden werden. Bei Forschungsreaktoren laesst sich sogar die Notkuehlung einfacher durchfuehren. (orig.)Original Title
Brennelement fuer Kernreaktoren
Primary Subject
Secondary Subject
Source
14 Dec 1978; 6 p; DE PATENT DOCUMENT 2063876/C/
Record Type
Patent
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Lee, Tae Hoon; Lee, Kiyoung; Shin, Young Joon; Lee, Min Koo
Proceedings of the KNS 2014 spring meeting2014
Proceedings of the KNS 2014 spring meeting2014
AbstractAbstract
[en] TRISO fuel particles are designed to not crack due to the stresses from processes (such as differential thermal expansion or fission gas pressure) at temperatures up to and beyond 1600 .deg. C, and therefore can contain the fuel in the worst of accident scenarios in a properly designed reactor. The TRISO fuel particles are fabricated into compacts and placed in a graphite block matrix in a prismatic block gas cooled reactor. TRISO fuel particles have been developed in the KAERI as part of the NHDD project. We expect the TRISO fuel compacts to be used in the Korean type VHTR reactor in the near future. Two of the major quality components are the sphericity and exact kernel size. Thus, we present a TRISO quality control method to improve the quality of TRISO and cope with continuous mass manufacturing production
Primary Subject
Source
Korean Nuclear Society, Daejeon (Korea, Republic of); [1 CD-ROM]; May 2014; [2 p.]; 2014 spring meeting of the KNS; Jeju (Korea, Republic of); 28-30 May 2014; Available from KNS, Daejeon (KR); 4 refs, 2 figs, 1 tab
Record Type
Miscellaneous
Literature Type
Conference
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