Germany
Decommissioning of the thorium high temperature reactor
(THTR 300)
Dietrich, G.; Neumann, W.; Roehl, N.
(Hochtemperatur-Kernkraftwerk GmbH, Hamm-Uentrop (Germany))
IAEA-TECDOC--1043, pp:9-15
Decommissioning of the AVR reactor, concept for the total dismantling
Marnet, C.; Wimmers, M. (AVR GmbH,
Duesseldorf (Germany)); Birkhold, U. (ISE GmbH (Germany))
IAEA-TECDOC--1043, pp:17-39
AVR decommissioning, achievements and future programme
Pohl, P. (Arbeitsgemeinschaft Versuchsreaktor AVR GmbH, Duesseldorf (Germany))
IAEA-TECDOC--1043, pp:41-53
The high temperature reactor (HTR) and the new German safety concept for future nuclear power plants
Haag, G.; Kugeler, K.; Philippen, P.W. (Forschungszentrum Juelich GmbH (Germany))
IAEA-TECDOC--901, pp:57-68
HTR plus modern turbine technology for higher efficiencies
Barnert, H.; Kugeler, K. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer
Sicherheitsforschung und Reaktortechnik)
IAEA-TECDOC--899, pp:67-82
Approach on a global HTGR R and D network
Lensa, W. von (Kernforschungszentrum Juelich GmbH, Juelich (Germany))
IAEA-TECDOC--988, pp:131-138
Unloading of the reactor core and spent fuel management of
THTR 300
Plaetzer, S.; Mielisch, M. (STEAG Kernenergie GmbH, Essen (Germany))
IAEA-TECDOC--1043, pp:143-150
R&D intermediate storage and final disposal of spent
HTR fuel
Fachinger, J.; Bruecher, H.; Duwe, R.
(Forschungszentrum Juelich, Juelich
(Germany))
IAEA-TECDOC--1043, pp:151-161
Experience with the interim storage of spent HTR fuel
elements and a view to necessary measures for final disposal
Niephaus, D.; Storch, S.; Halaszovich, S. (Forschungszentrum Juelich, Juelich (Germany))
IAEA-TECDOC--1043, pp:163-169
CASTOR THTR transport/storage casks
Laug, R.W.; Spilker, H. (Gesellschaft fuer
Nuklearbehaelter mbH, Essen (Germany));
Sappok, M. (Siempelkamp Giesserei GmbH
and Co., Krefeld (Germany))
IAEA-TECDOC--1043, pp:171-177
Potential and limitations in maximizing the power output of an inherent safe modular pebble bed HTGR
Scherer, W.; Ruetten, H.J.; Haas, K.A. (Kernforschungszentrum Juelich GmbH, Juelich
(Germany))
IAEA-TECDOC--988, pp:229-246
OTTO-PAP: An alternative option to the PBMR fuelling philosophy
Mulder, E. (AVR GmbH, Juelich (Germany)); Teuchert, E. (Kernforschungszentrum Juelich GmbH, Juelich (Germany))
IAEA-TECDOC--988, pp:247-262
Development and licensing of a melting plant for Chernobyl
scrap
Sappok, M. (Siempelkamp Nuclear- and Umwelttechnik GmbH and Co., Krefeld (Germany)); Zunk, H. (UNA GmbH, Kiew (Ukraine)); Fashevsky, K.A. (CPPRO, Chernobyl (Ukraine))
IAEA-TECDOC--1043, pp:257-267
Packaging requirements for graphite and carbon from the
decommissioning of the AVR in consideration of the German
final disposal regulations
Printz, R.J. (WTI GmbH, Juelich (Germany));
Quade, U. (SNU GmbH and Co., Krefeld
(Germany)); Wahl, J. (AVR GmbH, Juelich (Germany))
IAEA-TECDOC--1043, pp:275-286
Review of some aspects of radiological interest during the
establishment of the safe enclosure of the THTR 300 plant
Stratmann, W. (STEAG Kernenergie GmbH,
Essen (Germany)); Baechler, M. (Noell-KRC
Energie- and Umwelttechnik GmbH, Wuerzburg (Germany))
IAEA-TECDOC--1043, pp:287-294
Studies on self-acting heat removal systems on the basis of partial boiling of water for steel pressure vessel
cooling of modular HTRs
Barnert, H.; Singh, J. (Kernforschungszentrum Juelich GmbH, Juelich (Germany))
IAEA-TECDOC--988, pp:293-304
Results of cost estimates for the exploitation of the natural gas field in Indonesia using the HTR: A new
momentum for commercialization
Barnert, H. (Kernforschungszentrum Juelich GmbH, Juelich (Germany))
IAEA-TECDOC--988, pp:391-406
Microspheres of UO2, THO2 and PUO2 for the High Temperature Reactor
E. Brandau, Brace GmbH, Germany
HTR-2002, pp:1-5
Analysis of the European Results on the HTTR’s Core Physics Benchmarks
X. Raepsaet, F. Damian, CEN Saclay, France, U. A. Ohlig, H. J. Brockmann, Research Centre Jülich, Germany, J. B. M. De Haas, NRG/Petten and E. M. Wallerboss, Interfaculty Reactor Institute, Delft, The Netherlands
HTR-2002, pp:1-5
Three-Dimensional Numerical Simulation of Flow and Heat Transport in a High-Temperature Reactor
S. Becker and E. Laurien, Institute for Nuclear Technology & Energy Systems, Germany (IKE), University of Stuttgart, Germany
HTR-2002, pp:1-5
HTR-E Project: High Temperature Components and Systems
E. Beruil, FRAMATOME-ANP, France and R. Exner, Borsig Energy GmbH, Germany
HTR-2002, pp:1-5
EC-Funded Project (HTR-L) for the Definition of a European Safety Approach for HTR’s
S. Ehster, FRAMATOME-ANP, France, M. T. Dominguez, Empresarios Agrupados Internacional SA, I. Coe, NNC Ltd., United Kingdom, G. Brinkmann, FRAMATOME-ANP GmbH, Germany, W. von Lensa, Research Centre Jülich, Germany, W. van der Mheen, Nuclear Research and Consultancy Group, The Netherlands, C. Allessandroni, Ansaldo Nucleare, Italy and J. Pirson, Tractebel Energy Engineering, Belgium
HTR-2002, pp:1-6
Behaviour of spent HTR fuel elements in aquatic phases of repository host rock formations
J. Fachinger, S. Holgerson, M. Titov, T. Podruhzina, Research Centre Jülich, Jülich, GERMANY; M. den Exter, Nuclear Research and Consultancy Group-NRG, Petten, THE NETHERLANDS; B. Grambow; C. Landesmann, Ecole de Mines de Nantes, Nantes Cedex, FRANCE
HTR-2004, pp:1-22
Post-Irradiation Testing of HTR-Fuel Elements Under Accident Conditions. Part 2
Herbert Kostecka, John Ejton, Wim de Weerd, Enrique H. Toscano, EC, Joint Research Centre, European Institute for Transuranium, Karlsruhe, GERMANY
HTR-2004, pp:1-9
Novel Inert Matrix Fuel Kernels for Pu and Minor Actinide Incineration in High Temperature Reactors
J. Somers, A. Fernandez, Joint Research Centre, Institute for Transuranium Elements, Karlsruhe, GERMANY
HTR-2004, pp:1-11
HTR-N Reactor Physics and Fuel Cycle Studiies
J.C. Kuijper, J.B.M. de Haas, J. Oppe, NRG, Petten, THE NETHERLANDS; X. Raepsaet, F. Damian, F. Dolci, CEA, Saclay-Cadarache FRANCE; W. von Lensa, U. Ohlig, H.-J. Ruetten, H. Brockmann, Forschungszentrum Jülich, Jülich, GERMANY; W. Bernnat, Universität Stuttgart, IKE, Stuttgart, GERMANY; J.L. Kloosterman, Delft University of Technology, Delft, THE NETHERLANDS; N. Cerullo, G. Lomonaco, Universita di Pisa, Pisa, ITALY; A. Negrini, Ansaldo Energia S.p.A., Genova, ITALY; J. Magill, European Commision, JRC-ITU, Karlsruhe, GERMANY; R. Seiler, Paul Scherrer Institute, Villigen, SWITZERLAND
HTR-2004, pp:1-42
Coupling of Neutronics and Thermal-Hydraulics Codes For The Simulation of Transients of Pebble Bed HTR Reactors
T. Rademer, W. Bernnat, G. Lohnert, Institute of Nuclear Technology and Energy Systems (IKE), Stuttgart, GERMANY
HTR-2004, pp:1-15
Comparison of Two Models for a Pebble Bed Modular Reactor Core Coupled to a Brayton Cycle
Ayelet Walter, Alexander Schulz, Günter Lohnert, Intitute of Nuclear Technology and Energy Systems (IKE), Stuttgart, GERMANY
HTR-2004, pp:1-17
The Impact of Design on the Decay Heat Removal Capabilities of a modular Pebble Bed HTR
Nader Ben Said, Michael Buck, Wolfgang Bernnat, Günter Lohnert, Institute of Nuclear Technology and Energy Systems, Stuttgart, GERMANY
HTR-2004, pp:1-11
Thermal Response of a High Temperature Reactor during Passive Cooldown under Pressurized and Depressurized Conditions
Hamidul Haque, Wolfgang Feltes, Gerd Brinkmann, Framatome-ANP, Erlangen, GERMANY
HTR-2004, pp:1-17
Radioactive Waste Arising from HTR
J. Fachinger, H. Brücher, W. von Lensa, Institute for Safety Research and Reactor Technology, Forschungszentrum Jülich, Jülich, GERMANY; J.M. Turner, A. Nuttall, NNC Limited, Knutsford, UNITED KINGDOM; C. Bourdeloie, CEA Saclay, Gif sur Yvette, FRANCE; G. Brinkmann, Framatome-DE KWU NGES3, Erlangen, GERMANY
HTR-2004, pp:1-13
Recommendations for the development of high temperature reactors
D. Bastien (CEA), A. Chevalier (NNC), B.R.W. Haverkate (ECN), D. Hittner (Framatome), J. Magill (JRC/ITU), G. Proto (Ansaldo), H. Reutler (HTR-GmbH), N. Taylor (JRC/IAM) and W. von Lensa (FZj)
IAEA-TECDOC--1210, pp:9-22
Safety aspects of the operation experience with the AVR experimental power station
Ivens, G.; Ziermann, E. (Arbeitsgemeinschaft Versuchs-Reaktor G.m.b.H., Duesseldorf (Germany, F.R.))
IWGGCR--1, pp:10-15
Service conditions and relevant properties of HTGR metallic materials
Bodmann, E.; Diehl, H.; Blume-Firla, I.; Demus, H. (Hochtemperatur-Reaktorbau
GmbH, Mannheim (Germany, F.R.))
IWGGCR--18, pp:14-26
Requirements for electricity producing gas-cooled reactors in the
Federal Republic of Germany
Schwarz, D.K.J. (Vereinigte Elektrizitaetswerke Westfalen A.G.
(VEW), Dortmund (Germany, F.R.))
IWGGCR--19, pp:14-17
Principles of decay heat removal in reactor technology - Present status and future prospects
Kugeler, K. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer
Sicherheitsforschung und Reaktortechnik)
IAEA-TECDOC--757, pp:15-29
Operational monitoring of the release behaviour of the AVR
core
Wawrzik, U.; Ivens, G. (Arbeitsgemeinschaft
Versuchsreaktor AVR, Juelich (Germany))
IWGGCR--13, pp:15-26
Accident analysis and accident control for the THTR - 300 power plant
Breitenfelder, R.; Wachholz, W.; Weicht, U. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.))
IWGGCR--1, pp:16-22
Fuel irradiation experiments on HFR-K6 and HFR-B1 with intermittent water vapour injections
Nabielek, H. (Forschungszentrum Juelich GmbH (Germany)); Conrad, R. (Joint Research
Centre, Petten (Netherlands)); Roellig, K. (ABB Kraftwerke AG, Mannheim (Germany)); Meyers, B.F. (Oak Ridge National Lab., TN (United States))
IAEA-TECDOC--784, pp:17-24
Experimental and theoretical analysis of spent AVR fuels.
Werner, H.; Thomas, F. (Forschungszentrum Juelich GmbH
(Germany, F.R.)); Woloch, F.; Reitsamer, G.; Falta, G.; Strigl,
A. (Oesterreichisches Forschungszentrum Seibersdorf GmbH
(Austria))
IWGGCR--24, pp:19-30
Operational requirements of spherical HTR fuel elements and their performance
Roellig, K.; Theymann, W. (Hochtemperatur-Reaktorbau
GmbH, Mannheim (Germany))
IWGGCR--8, pp:19-39
Application of the high temperature reactor in the energy economy
Kugeler, K.; Barnert, H. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer
Sicherheitsforschung und Reaktortechnik)
IAEA-TECDOC--761, pp:23-33
Two decades of excellent AGR circulator operating performance at AVR Juelich
Ziermann, E.L. (Arbeitsgemeinschaft Versuchs-Reaktor G.m.b.H., Juelich (Germany, F.R.)); Engel, J. (Brown, Boveri und Cie A.G., Mannheim (Germany, F.R.))
IWGGCR--17, pp:23-30
Process heat supply requirements on HTGRs
Schad, M.K. (Lurgi GmbH, Frankfurt am Main (Germany,
F.R.))
IWGGCR--19, pp:24-29
HTR fuel element development in the Federal Republic of
Germany
Balthesen, E. (Forschungszentrum Juelich GmbH (Germany))
IWGGCR--25, pp:24-25
Experimental facilities for plate-out investigations and future work
Muenchow, K.; Dederichs, H.; Iniotakis, N.; Sackmann, B. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IWGGCR--2, pp:26-34
The release of iodine from HTR fuel under steady-state and
transient conditions
Christ, A. (Hochtemperatur Reaktorbau GmbH,
Mannheim (Germany)); Mehner, W.; Schenk, W.
(KFA Juelich (Germany))
IWGGCR--13, pp:27-40
Earthquake analysis with nonlinear soil-structure interaction and
nonlinear supports of components.
Hansson, V. (Strabag Bau-AG, Koeln (Germany, F.R.))
IWGGCR--22, pp:27-34
Safety concept of high-temperature reactors based on the experience with AVR and THTR
Wachholz, Winfried (Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany)); Kroeger, Wolfgang (Institut fuer Nukleare Sicherheitsforschung, Kernforschungsanlage Juelich (Germany))
IAEA-TC--389.26, pp:31-40
Contribution of earthquakes to the risk of a HTR-100 plant.
Altes, J. (Kernforschungsanlage Juelich GmbH (Germany,
F.R.). Inst. fuer Nukleare Sicherheitsforschung)
IWGGCR--22, pp:34-41
Results from plate-out investigations
Iniotakis, N.; Malinowski, J.; Gottaut, H.; Muenchow, K. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IWGGCR--2, pp:35-43
Progress and problems in modelling HTR core dynamics. The
TINTE code tested at AVR power transients
Scherer, W.; Gerwin, H. (Forschungszentrum Juelich GmbH
(Germany, F.R.). Inst. fuer Sicherheitsforschung und
Reaktortechnik)
IWGGCR--24, pp:36-42
Status of the R&D programme in the field of the heat carrying and heat transfer components of the PNP project
Mausbeck, H.; Jansing, W. (INTERATOM GmbH,
Bergisch-Gladbach (Germany))
IWGGCR--9, pp:36-47
Analysis of nuclear graphite core components in HTRs and a critique on conventional approaches
Willaschek, J.G. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))
IWGHTR--3, pp:36-41
Simulation of steam ingress accidents with irradiated fuel elements
Schenk, W.; Nabielek, H. (Forschungszentrum Juelich GmbH (Germany))
IAEA-TECDOC--784, pp:37-44
Mechanical design philosophy for the graphite components of the core structure of an HTGR
Bodmann, E. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.))
IWGGCR--11, pp:37-42
Circulator performance during THTR trial and post-commissioning operation
Glahe, E. (Hochtemperatur-Kernkraftwerk G.m.b.H. (HKG), Hamm (Germany, F.R.)); Stoelzl, D. (Brown, Boveri und Cie A.G., Mannheim (Germany, F.R.))
IWGGCR--17, pp:39-47
Modelling of fission product release behavior from HTR
spherical fuel elements under accident conditions.
Verfondern, K.; Mueller, D. (Forschungszentrum Juelich GmbH
(Germany). Inst. fuer Sicherheitsforschung und Reaktortechnik)
IWGGCR--25, pp:45-55
Basic lay-out, arrangement and design criteria of heat components of the ''nuclear coal gasification
prototype plant (PNP)''
Pruschek, R. (Gesellschaft fuer Hochtemperaturreaktor-Technik m.b.H., Bergisch Gladbach
(Germany, F.R.))
IWGHTR--6, pp:45-51
The ultimate safety of the HTR-Module during hypothetical accidents
Lohnert, G.H. (Siemens AG Unternehmensbereich KWU, Bergisch Gladbach
(Germany). Bereich Energieerzeugung, Nukleare Entsorgung und
Entwicklungsprojekte)
IAEA-TECDOC--757, pp:47-50
Design requirements on HTR main components for process heat application
Dumm, K. (INTERATOM GmbH, Bergisch-Gladbach
(Germany))
IWGGCR--9, pp:48-64
Structural instabilities of high temperature alloys and their use in advanced high temperature gas
cooled reactors
Schuster, H.; Ennis, P.J.; Nickel, H. (Kernforschungsanlage Juelich GmbH
(Germany, F.R.). Inst. fuer Reaktorwerkstoffe); Czyrska-Filemonowicz, A.
(Akademia Gorniczo-Hutnicza, Cracow (Poland). Inst. Metalurgii)
IWGGCR--18, pp:50-50
Correlation between microstructure and the creep behaviour at high temperature of Alloy 800 H
Spiradek, K. (Institute of Nuclear Physics, Cracow (Poland)); Degischer, H.P.
(Aluminium Ranshofen GmbH, Ranshofen (Austria)); Lahodny, H.
(Max-Planck-Institut fuer Metallforschung, Stuttgart (Germany, F.R.))
IWGGCR--18, pp:51-62
Analysis of the stresses in a side reflector block of the pebble bed reactor
Schmidt, A. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.))
IWGHTR--3, pp:51-62
Materials evaluation and development for HTR-nuclear process heat application
Nickel, H.; Schubert, F.; Schuster, H. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)); Grosser, E.D. (Gesellschaft fuer Hochtemperaturreaktor-Technik m.b.H., Bergisch
Gladbach (Germany, F.R.); Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch
Gladbach (Germany, F.R.)); Theymann, W. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim
(Germany, F.R.))
IWGHTR--6, pp:52-61
Distribution of the decay heat in various module HTRs and influence on peak fuel temperatures
Teuchert, E.; Haas, K.A.; Heek, A. van (Forschungszentrum Juelich GmbH
(Germany)); Kasten, P.R. (Tennessee Univ., Knoxville, TN (United States))
IAEA-TECDOC--757, pp:53-62
Twenty-five years of Brown Boveri experience in development, design and fabrication of circulators for HTGR
Stoelzl, D. (Brown, Boveri und Cie A.G., Mannheim (Germany, F.R.))
IWGGCR--17, pp:53-59
The NACOK experiment on natural convection of air through the core
Froehling, W.; Hohn, H.; Kugeler, M. (Forschungszentrum Juelich GmbH (Germany));
Sun, Y.; Zhang, Z. (Institute of Nuclear Energy Technology, Beijing (China))
IAEA-TECDOC--784, pp:55-61
Burst tests to measure the tangential strength of CFC tubes
Roedig, M.; Woschek, B. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer
Reaktorwerkstoffe); Baur, W. (SIGRI GmbH, Meitingen (Germany))
IAEA-TECDOC--690, pp:59-63
Safety-related experiences with the AVR reactor
Krueger, K.J.; Ivens, G.P. (Arbeitsgemeinschaft Versuchs-Reaktor G.m.b.H.,
Duesseldorf (Germany, F.R.))
IAEA-TECDOC--358, pp:61-70
The present state of the HTR concept based on experience
gained from AVR and THTR
Wachholz, W. (Hochtemperatur-Reaktorbau G.m.b.H.,
Mannheim (Germany, F.R.))
IWGGCR--19, pp:61-70
Helium/helium heat exchangers and hot-gas ducts for the PNP-project according to the BBC/HRB concept
Schmitt, H.; Juergens, B.; Knaul, J.
(Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany))
IWGGCR--9, pp:65-81
Heat treatment of graphite and resulting tritium emissions
J. Wörner, W. Botzem, S.D. Preston
TCM-Manchester99, pp:65-76
Fission product behaviour in the primary circuit of an HTR
Decken, C.B. von der; Iniotakis, N. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IWGGCR--2, pp:68-74
Considerations on the design of a helium circulator for a high temperature modular reactor system
Dumm, K. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.)); Donaldson, J. (James Howden and Co. Ltd, Renfrew (UK))
IWGGCR--17, pp:69-76
Corrosion behaviour of high temperature alloys in the cooling gas of high temperature reactors
Quadakkers, W.J.; Schuster, H. (Kernforschungsanlage Juelich GmbH (Germany,
F.R.). Inst. fuer Reaktorwerkstoffe)
IWGGCR--18, pp:69-74
Heat-exchanging components for coal gasification: He/He intermediate heat exchanger (IHX) and
steam reformer (STR) in the primary circuit
Niemeyer, W. (Gesellschaft fuer Hochtemperaturreaktor-Technik m.b.H., Bergisch Gladbach
(Germany, F.R.))
IWGHTR--6, pp:71-77
Results of a German probabilistic risk assessment study for the HTR-1160 concept
Fassbender, J.; Kroeger, W. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Nukleare Sicherheitsforschung)
IWGGCR--1, pp:73-87
Fracture mechanics applied to a reactor graphite
Roedig, M.; Kleist, G.; Nickel, H. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IWGHTR--3, pp:76-88
Main circulator design features for HTR 100, HTR 500 and space heating plants
Engel, J.; Glass, D. (Brown, Boveri und Cie A.G., Mannheim (Germany, F.R.))
IWGGCR--17, pp:77-82
Scenarios of hypothetical water and air ingress in small modular HTGRs
Scherer, W.; Gerwin, H. (Forschungszentrum Juelich GmbH (Germany))
IAEA-TECDOC--784, pp:79-85
The influence of dust on the hazard potential of a depressurization accident of a high temperature reactor
Iniotakis, N.; Decken, C.B. von der (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IWGGCR--2, pp:81-87
Spherical coated particle fuel for fuel elements of HTGR
Chernikov, A.S.; Permyakov, L.N.; Mikhailichenko, L.I.;
Nezhevenko, L.B.; Gudovich, A.P.; Landin, N.A.; Ljutikov,
R.A.; Solovjev, G.I
IWGGCR--8, pp:81-98
Investigations of an emergency shut-down system using small absorbing spheres for
pebble-bed high temperature gas-cooled reactors
Ninaus, W.; Sgouridis, S.; Schuerrer, F.; Mueller, H.J.; Oswald, K.
(Technische Univ., Graz (Austria). Inst. fuer Theoretische Physik und
Reaktorphysik); Neef, R.D.; Schall, H. (Kernforschungsanlage Juelich G.m.b.H.
(Germany, F.R.). Inst. fuer Reaktorentwicklung)
IAEA-TECDOC--358, pp:85-94
First operating experience with the steam generators of the THTR nuclear power plant
Elter, C.; Juergens, B. (Hochtemperatur-Reaktorbau GmbH, Mannesheim (Germany)); Schaer, G. (Sulzer Brothers Ltd., Winterthur (Switzerland))
IWGGCR--15, pp:86-97
Status of development of the HTR module
Weisbrodt, I.A. (Internationale Atomreaktorbau G.m.b.H.
(INTERATOM), Bergisch Gladbach (Germany, F.R.))
IWGGCR--19, pp:86-96
Efficiency of inherent protection mechanisms for an improved HTR safety concept
Petersen, K.; Buescher, R.; Gerwin, H.; Schenk, W. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung)
IWGGCR--1, pp:87-95
Testing of irradiated spherical fuel elements at HTR MODUL
relevant accident conditions.
Schenk, W.; Nabielek, H. (Forschungszentrum Juelich GmbH,
Juelich (Germany). Inst. fuer Reaktorwerkstoffe und
HTA-Projekt)
IWGGCR--25, pp:87-98
Trends in safety criteria for future reactor plants
Hicken, E. (Forschungszentrum Juelich GmbH (Germany). Inst. fuer
Sicherheitsforschung und Reaktortechnik)
IAEA-TECDOC--757, pp:89-92
Evaluation of mechanical properties of the alloy NiCr22Co12Mo (Alloy 617) for heat
exchanging components of HTGRs
Breitling, H.; Dietz, W. (Internationale Atomreaktorbau GmbH (INTERATOM),
Bergisch Gladbach (Germany, F.R.)); Penkalla, H.J. (Kernforschungsanlage
Juelich GmbH (Germany, F.R.). Inst. fuer Reaktorwerkstoffe)
IWGGCR--18, pp:91-99
Impact of different libraries on the performance calculation of a
modul-type pebble bed HTR.
Ohlig, U.; Brockmann, H.; Haas, K.A.; Teuchert, E.
(Forschungszentrum Juelich GmbH (Germany, F.R.). Inst. fuer
Sicherheitsforschung und Reaktortechnik)
IWGGCR--24, pp:92-98
Inert annealing of irradiated graphite by inductive heating
W. Botzem, J. Wörner
TCM-Manchester99, pp:92-104
Development of a helium/helium intermediate heat exchanger with helical coil tube bundle
Czimczik, A. (L. and C. Steinmueller GmbH, Gummersbach
(Germany)); Hirschle, G. (Gebr. Sulzer AG, Winterthur
(Switzerland))
IWGGCR--9, pp:94-115
Analytical and experimental investigations of the passive heat transport in HTRs under severe
accident conditions
Rehm, W.; Barthels, H.; Jahn, W. (Forschungszentrum Juelich GmbH
(Germany)); Cleveland, J. (Oak Ridge National Lab., TN (United States));
Ishihara, M. (Japan Atomic Energy Research Inst., Ibaraki (Japan))
IAEA-TECDOC--757, pp:95-103
Model experiments on depressurisation accidents in nuclear process heat plants (HTGR)
Fritsching, G.; Wolf, G. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))
IWGGCR--1, pp:95-101
Mechanical design of the hot steam headers of the THTR-300 steam generators
Blumer, U. (Sulzer Brothers Ltd., Winterthur (Switzerland)); Stumpf, M. (EVT Stuttgart, Stuttgart (Germany))
IWGGCR--15, pp:97-106
Plate-out measurements and decontamination of a component of the AVR reactor at Juelich
Hanulik, J.; Schmied, H.; Wahl, J. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IWGGCR--2, pp:99-106
The THTR-300 coolant gas activity, an indicator of fuel
performance
Roellig, K. (Hochtemperatur-Reaktorbau GmbH, Mannheim
(Germany))
IWGGCR--25, pp:99-108
HTR fuel manufacturing experience
Heit, W.; Huschka, H.; Mehner, A.W. (HOBEG mbH, Hanau
(Germany))
IWGGCR--8, pp:99-105
Multiaxial creep of tubes of Alloy 800 and Alloy 617 at high temperature
Penkalla, H.J.; Schubert, F.; Nickel, H. (Kernforschungsanlage Juelich GmbH
(Germany, F.R.). Inst. fuer Reaktorwerkstoffe)
IWGGCR--18, pp:100-110
Glas generator for the steam gasification of coal with nuclear generated heat
Buchner, G. (Mannesmann Anlagenbau A.G., Duesseldorf (Germany, F.R.))
IWGHTR--6, pp:102-110
Notes on HTR applications in methanol production
Santoso, B. (National Atomic Energy Agency, Jakarta (Indonesia)); Barnert, H.
(Forschungszentrum Juelich GmbH (Germany))
IAEA-TECDOC--923, pp:103-112
Irradiation creep performance of graphite relevant for pebble bed HTRs
Kleist, G.; O'Connor, M.F. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IWGHTR--3, pp:103-110
The structure of risk caused by accidents in small and medium HTRs
Kroeger, W.; Mertens, J.; Wolters, J. (Kernforschungsanlage Juelich G.m.b.H.
(Germany, F.R.). Inst. fuer Nukleare Sicherheitsforschung)
IAEA-TECDOC--358, pp:105-108
Safety analysis of small and medium HTRs under core-cooling accident conditions
Rehm, W.; Altes, J.; Breitbach, G.; Nabbi, R.; Verfondern, K.
(Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Nukleare
Sicherheitsforschung)
IAEA-TECDOC--358, pp:109-119
The HTR safety concept demonstrated by selected examples
Sommer, H.; Stoelzl, D. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.))
IWGGCR--1, pp:110-117
A statistical fracture criterion for graphite
Cords, H.; Kleist, G.; Zimmermann, R. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IWGHTR--3, pp:110-115
Design of steam generators for process heat plants: Requirements, design concepts, status and
further development
Rautenberg, J. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.))
IWGHTR--6, pp:111-119
A German research project about applicable graphite cutting techniques
D. Holland, U. Quade, F.W. Bach, P. Wilk
TCM-Manchester99, pp:114-124
Steam generator design and development for a helium-cooled modular HTR
Dumm, K.; Zipper, E. (Interatom GmbH, Bergisch Gladbach (Germany)); Keintzel, G. (L. and C. Steinmueller GmbH, Gummersbach (Germany))
IWGGCR--15, pp:115-123
Maintenance concept of the gas turbine in a 1640 MW direct cycle HTR
Schmied, H.; Karaus, H. (Brown Boveri and Company Ltd., Baden, Germany, F.R.); Roellig, K. (Hochtemperatur-Reaktorbau
G.m.b.H., Mannheim (Germany, F.R.)); Schenker, E. (Eidgenoessisches Inst. fuer Reaktorforschung, Wuerenlingen (Switzerland))
IWGGCR--2, pp:118-125
Seismic behavior of the core cavern of a HTGR with pebble bed core
Kleine-Tebbe, K.A.; Kemter, F. (Hochtemperatur-Reaktorbau GmbH, Julich, Germany)
IWGGCR--6, pp:119-132
Ceramic coatings for HTR graphitic structures
Hurtado, A.M. (Aachen Univ., Aachen (Germany). Inst. of Reactor Safety and Technology); Schroeder, B.; Gottaut, H. (Forschungszentrum Juelich GmbH (Germany))
IAEA-TECDOC--784, pp:120-124
Aspects of water and air ingress accidents in HTRs
Wolters, J. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Nukleare Sicherheitsforschung)
IWGGCR--1, pp:124-131
Analysis of the steam generator for the GCR-module
Podhorsky, M. (Balcke-Duerr AG, Ratingen (Germany))
IWGGCR--15, pp:124-129
Post-service examination of a 10 MW helium-helium heat exchanger and comparison with long
term behaviour in laboratory tests
Cook, R.H.; Graham, L.W. (R.M. Detection Ltd, Poole, Dorset (UK). High
Temperature Materials Programme (HTMP)); Exner, R. (Balcke-Duerr AG,
Ratingen (Germany, F.R.))
IWGGCR--18, pp:124-130
Dynamic testing and qualification.
Kleine Tebbe, A.; Schmidt, G.; Theymann, W.
(Hochtemperatur-Reaktorbau GmbH, Juelich (Germany, F.R.))
IWGGCR--22, pp:125-132
Development and testing of nuclear graphite for the German pebble-bed high temperature reactor
Haag, G.; Delle, W.; Nickel, H. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)); Theymann, W.; Wilhelmi, G
IWGGCR--11, pp:128-132
Analysis and manufacture of the HTR-100 steam generator
Exner, R. (Balcke-Duerr AG, Ratingen (Germany))
IWGGCR--15, pp:130-140
Development of an inactive heat removal system for high temperature reactors
Kugeler, K. (Rheinisch-Westfaelische Technische Hoschschule, Aachen
(Germany)); Sappok, M.; Beine, B. (Siempelkamp Giesserei GmbH und Co.,
Krefeld (Germany)); Wolf, L. (Battelle-Institut e.V., Frankfurt am Main
(Germany))
IAEA-TECDOC--757, pp:131-139
Creep and fatigue crack growth in tubes of HTR components
Roedig, M.; Pfaffelhuber, M.; Schubert, F.; Nickel, H. (Kernforschungsanlage
Juelich GmbH (Germany, F.R.). Inst. fuer Reaktorwerkstoffe); Bodmann, E.
(Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany, F.R.))
IWGGCR--18, pp:131-144
Results from integral tests of single reformer tubes under simulated nuclear reactor conditions
Decken, C.B. von der; Fedders, H.; Harth, R.; Hoehlein, B.; Riensche, E. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IWGHTR--6, pp:134-142
Chemical reactions during nuclear drying of the AVR primary circuit following a water ingress
Nieder, R.; Vey, K. (Arbeitsgemeinschaft Versuchs-Reaktor G.m.b.H., Juelich (Germany, F.R.))
IWGGCR--2, pp:137-144
Passive heat removal experiments for an advanced HTR-module reactor pressure vessel and
cavity design
Wolf, L.; Kneer, A.; Schulz, R.; Giannikos, A.; Haefner, W. (Battelle-Institut
e.V., Frankfurt am Main (Germany))
IAEA-TECDOC--757, pp:139-146
Development, construction and analysis of the URKO intermediate heat
exchanger
Exner, R.; Podhorsky, M. (Balcke-Duerr AG, Ratingen
(Germany))
IWGGCR--9, pp:139-170
Steam generator concept of a small HTR for reheating and for removal of the residual heat
Singh, J.; Barnert, H.; Hohn, H.; Mondry, M. (Institut fuer Reaktorenentwicklung, Kernforschungsanlage Juelich GmbH, Juelich (Germany))
IWGGCR--15, pp:141-146
Mechanical design aspects of HTR-heat exchanger components: Description of loading
conditions, discussion of failure modes, design criteria and present status of mechanical design
work
Seehafer, H.J. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach
(Germany, F.R.))
IWGHTR--6, pp:142-150
HTR process heat applications, status of technology and economical potential
Barnet, H. (Forschungszentrum Juelich GmbH (Germany))
IAEA-TECDOC--923, pp:143-163
Safety criteria for advanced HTGR concepts
Kroeger, W. (Kernforschungsanlage Juelich G.m.b.H. (Germany,
F.R.). Inst. fuer Nukleare Sicherheitsforschung)
IWGGCR--19, pp:143-152
Fracture mechanical characteristic values (J-integral) with transference to components (tubes) by
an analytical method
Ullrich, G.; Alder, H.P. (Paul Scherrer Inst. (PSI), Wuerenlingen (Switzerland));
Huthmann, H.; Grueter, L. (Internationale Atomreaktorbau GmbH
(INTERATOM), Bergisch Gladbach (Germany, F.R.))
IWGGCR--18, pp:144-151
Predictions on an HTR coolant composition after operational experience with experimental reactors
Nieder, R. (Arbeitsgemeinschaft Versuchs-Reaktor G.m.b.H., Juelich (Germany, F.R.))
IWGGCR--2, pp:144-152
Summary of discussion of the future HTGR PROTEUS experiments
and other planned experiments.
Scherer, W. (Forschungszentrum Juelich GmbH (Germany,
F.R.))
IWGGCR--24, pp:145-147
Safety concept and design of a modular gas cooled high-temperature reactor from the viewpoint of
externally generated load cases
Peters, K.; Mueller-Frank, U.; Steinwarz, W. (Interatom, Bensberg, Germany)
IWGGCR--6, pp:147-160
SANA experiments related to self-operating removal of decay heat
Niessen, H.F.; Lange, M.G. (Forschungszentrum Juelich GmbH (Germany).
Inst. fuer Sicherheitsforschung und Reaktortechnik)
IAEA-TECDOC--757, pp:151-160
Fracture toughness of Alloy 800 H at room temperature
Krompholz, K.; Ullrich, G.; Alder, H.P. (Paul Scherrer Inst. (PSI), Wuerenlingen
(Switzerland)); Gnirss, G. (Asea Brown Boveri AG, Mannheim (Germany, F.R.));
Huthmann, H. (Internationale Atomreaktorbau GmbH (INTERATOM), Bergisch
Gladbach (Germany, F.R.)); Roedig, M.; Schubert, F. (Kernforschungsanlage
Juelich GmbH (Germany, F.R.). Inst. fuer Reaktorwerkstoffe)
IWGGCR--18, pp:153-162
Tritium behaviour in an HTR-system based on AVR-experience
Steinwarz, W. (Gesellschaft fuer Hochtemperaturreaktor-Technik m.b.H., Bergisch Gladbach (Germany, F.R.)); Roehrig, H.D.
(Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)); Nieder, R. (Arbeitsgemeinschaft Versuchs-Reaktor G.m.b.H., Juelich
(Germany, F.R.))
IWGGCR--2, pp:153-160
Radiochemical characterisation of graphite from Jülich experimental reactor (AVR)
B. Bisplinghoff, M. Lochny, J. Fachinger, H. Brücher
TCM-Manchester99, pp:153-159
Safety concepts of present HTR-plants
Wachholz, W. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.))
IAEA-TECDOC--358, pp:155-156
HTR fuel: prediction of fission product release in accidents
Nabielek, H.; Verfondern, K. (KFA Juelich
(Germany)); Goodin, D.T. (GA Technologies
(United States))
IWGGCR--13, pp:155-169
Operational experience with HTR-fuel in the AVR experimental power station
Ivens, G.; Wimmers, M. (Arbeitsgemeinschaft
Versuchsreaktor (AVR) GmbH, Juelich (Germany))
IWGGCR--8, pp:161-173
The new alloy Thermon 4972 (NiCr22W12Fe) for high temperature components of gas-cooled
reactors
Huchtemann, B. (Thyssen Edelstahlwerke AG, Krefeld (Germany, F.R.))
IWGGCR--18, pp:162-175
Storage and final disposal of spent HTR fuel in the Federal
Republic of Germany
Kirch, N.; Brinkmann, H.U. (Kernforschungsanlage Juelich
G.m.b.H. (Germany, F.R.))
IWGGCR--19, pp:163-175
Development of a new type of high-temperature insulation material and its application in the PNP project
Burger, R.; Ganz, R. (Didier-Werke AG, Dept.
Energie-Technik, Wiesbaden (Germany))
IWGGCR--9, pp:171-191
HTR coated particle fuel: irradiation behaviour and performance prediction
Burck, W.; Nabielek, H. (KFA, Juelich (Germany)); Christ,
A. (HRB, Mannheim (Germany)); Ragoss, H. (GHT,
Bensberg (Germany)); Mehner, A.W. (HOBEG, Hanau
(Germany))
IWGGCR--8, pp:174-188
Design status of the HTR 500 power plant and the HTR module power plant
Arndt, E.; Fischer, R. (Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany, F.R.))
IAEA-TC--389.26, pp:175-211
Comparison of mechanical and corrosion behaviour of Alloy 800 H and the new alloy AC 66
Pelz, W. (Bergbau-Forschung GmbH, Essen (Germany, F.R.)); Schendler, W.;
Weber, H. (Mannesmann-Roehrenwerke AG, Duisburg (Germany, F.R.))
IWGGCR--18, pp:176-183
Graphite corrosion under severe HTR accident conditions
Katscher, W.; Moormann, R. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IWGGCR--11, pp:182-188
The spherical fuel element as extremely effective barrier for
fission products in the HTR module
Allelein, H.J.; Quade, U. (Interatom GmbH,
Bergisch Gladbach (Germany))
IWGGCR--13, pp:182-207
Influence of the yaw angle on heat transfer and pressure drop of helical type heat exchangers
Groehn, H.G. (Institut fuer Reaktorbauelemente, Kernforschungsanlage Juelich GmbH, Juelich (Germany))
IWGGCR--15, pp:182-188
Results of the safety evaluation for the AVR-modification into a nuclear process heat plant
Kirch, N. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.))
IAEA-TECDOC--358, pp:183-192
Experimental and theoretical work for the analysis of creep ratcheting and creep buckling of
HTR components
Breitbach, G.; Schubert, F.; Nickel, H. (Kernforschungsanlage Juelich GmbH
(Germany, F.R.). Inst. fuer Reaktorwerkstoffe); Seehafer, H.J. (Internationale
Atomreaktorbau GmbH (INTERATOM), Bergisch Gladbach (Germany, F.R.))
IWGGCR--18, pp:183-190
Development and validation of an improved creep-fatigue interaction rule for
lifetime determination of high temperature components
Lehmann, H.J.; Becker, M.; Luedeke, M. (Rheinisch-Westfaelischer Technischer
Ueberwachungs-Verein e.V., Essen (Germany, F.R.))
IWGGCR--18, pp:190-194
Dispersion of hot spots in steam generators
Achenbach, E.J. (Institut fuer Reaktorbauelemente, Kernforschungsanlage Juelich GmbH, Juelich (Germany))
IWGGCR--15, pp:194-199
Thermohydraulic verification during THTR steam generator commissioning
Henry, C. (Sulzer Brothers Ltd., Winterthur (Switzerland)); Elter, C. (Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany))
IWGGCR--15, pp:204-210
Core heat up accident simulation with HTR fuel elements
Nabielek, H.; Schenk, W.; Verfondern, K. (Kernforschungsanlage Juelich
G.m.b.H. (Germany, F.R.))
IAEA-TECDOC--358, pp:213-225
Frequency and distribution of leakages in steam generators of gas-cooled reactors
Bongratz, R.; Breitbach, G.; Wolters, J. (Institut fuer Nukleare Sicherheitsforschung, Kernforschungsanlage Juelich GmbH, Juelich (Germany))
IWGGCR--15, pp:215-222
Dynamic simulation of steam generator failures
Meister, G. (Institut fuer Nukleare Sicherheitsforschung, Kernforschungsanlage Juelich GmbH, Juelich (Germany))
IWGGCR--15, pp:222-233
Investigations on the water ingress in a pebble-bed high temperature gas-cooled reactor
Mueller, H.J.; Ninaus, W.; Schuerrer, F.; Rabitsch, H. (Technische Univ., Graz
(Austria). Inst. fuer Theoretische Physik und Reaktorphysik); Neef, R.D.
(Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.). Inst. fuer
Reaktorentwicklung)
IAEA-TECDOC--358, pp:227-234
Use of plutonium in pebble bed HTGRs
K.Kugeler, W.von Lensa, G. Haag, H.J. Rütten (Institute for Safety Research and Reactor Technology, Forschungszentrum Juelich GmbH, Germany)
IAEA-TECDOC--1210, pp:229-236
Investigations of gas explosions in a nuclear coal gasification plant
Schulte, K. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM), Bergisch Gladbach (Germany, F.R.))
IWGGCR--1, pp:233-253
The corrosional and nuclear effects of water ingress into the primary circuit of an HTR-module
Lohnert, G.H. (Internationale Atomreaktorbau G.m.b.H. (INTERATOM),
Bergisch Gladbach (Germany, F.R.))
IAEA-TECDOC--358, pp:235-236
Control of the tritium path in process heat HTR's
Kirch, N.; Scheidler, G. (KFA Juelich (Germany))
IWGGCR--13, pp:236-249
Air and water ingress accidents in a HTR-module of side-by-side concept
Wolters, J.; Breitbach, G.; Moormann, R. (Kernforschungsanlage Juelich
G.m.b.H. (Germany, F.R.). Inst. fuer Nukleare Sicherheitsforschung)
IAEA-TECDOC--358, pp:237-249
Sustainability and acceptance - new challenges for nuclear energy
W. von Lensa (Institute for Safety Research and Reactor Technology, Forschungszentrum Juelich GmbH, Germany)
IAEA-TECDOC--1210, pp:237-246
Results of the visual in-pile inspection of the inner graphite reflector of the AVR
Haag, G.; Delle, W.; Kirch, N.; Nickel, H. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)); Reinhart, K.; Ziermann, E
IWGGCR--11, pp:239-242
The properties of spherical fuel elements and its behavior in the modular HTR
Lohnert, G.H.; Ragoss, H. (INTERATOM GmbH, D-5060
Bergisch Gladbach 1 (Germany))
IWGGCR--8, pp:244-254
The gas-breeder memorandum and the research and development programme of the Federal Republic of Germany in the field of gas-cooled fast reactors
Dalle Donne, M. (Kernforschungszentrum Karlsruhe (F.R. Germany). Inst. fuer Neutronenphysik und Reaktortechnik)
IAEA-TECDOC--154, pp:264-285
The behaviour of spherical HTR fuel elements under accident conditions
Schenk, W.; Naoumidis, A. (Institute for Reactor Material,
KFA Juelich (Germany))
IWGGCR--8, pp:264-280
Core physics tests of THTR pebble bed core at zero power
Brandes, S. (Hochtemperatur-Reaktorbau G.m.b.H., Mannheim (Germany, F.R.))
IAEA-TECDOC--358, pp:285-298
Development and fabrication of a helium-heated steam reformer
Panknin, W.; Nowak, W. (L and C Steinmueller GmbH,
Gummersbach (Germany))
IWGGCR--9, pp:288-301
''Peu a peu'': A new fuelling mode of the pebble bed reactor
Teuchert, E.; Gerwin, H.; Haas, K.A.; Ruetten, H.J. (Kernforschungsanlage
Juelich G.m.b.H. (Germany, F.R.). Inst. fuer Reaktorentwicklung)
IAEA-TECDOC--358, pp:299-311
Assembly and operation experience of EVA II steam reforming bundle
Niessen, H.F.; Harth, R. (Kernforschungsanlage Juelich GmbH,
Juelich (Germany)); Kesel, W. (Rheinische Braunkohlenwerke
AG, Koeln (Germany))
IWGGCR--9, pp:302-308
Research, development and demonstration work on interim and final storage of HTR fuel elements
Kaiser, G.; Brinkmann, U. (Kernforschungsanlage Juelich
GmbH, Projektleitung
Hochtemperaturreaktor-Brennstoffkreislauf, Juelich
(Germany)); Duwe, R. (Kernforschungsanlage Juelich GmbH,
Institut fuer Reaktorwerkstoffe, Juelich (Germany))
IWGGCR--8, pp:303-314
Evaluation of materials for heat exchanging components in advanced helium-cooled reactors
Schubert, F. (Kernforschungsanlage Juelich GmbH, Institut fuer
Reaktorwerkstoffe, Juelich (Germany))
IWGGCR--9, pp:309-334
Utilization of process heat from the HTR in the chemical and related industries
Schad, M.; Didas, U.; Ebeling, F.; Kreutzkamp, G.; Renner, H
IAEA-TC--389.26, pp:328-339
Caesium deposition on HTR primary circuit materials
Roellig, K.; Christ, A.; Haase, F.W.; Wiedmann,
J. (Hochtemperatur-Reaktorbau GmbH,
Mannheim (Germany))
IWGGCR--13, pp:329-350
Chemical processing of HTR fuels applying either THOREX or PUREX flow sheets
Zimmer, E.; Merz, E. (Kernforschungsanlage, Juelich GmbH,
Institut fuer Chemische Technologie der Nuklearen
Entsorgung, Juelich (Germany))
IWGGCR--8, pp:333-344
Pressure vessel design codes: A review of their applicability to HTGR components at temperatures above 800 deg C
Hughes, P.T. (General Electric Co., Sunnyvale, CA (United
States)); Over, H.H. (Kernforschungsanlage Juelich GmbH,
IRW, Juelich (Germany)); Bieniussa, K. (Gesellschaft fuer
Reaktorsicherheit mbH, Koeln (Germany))
IWGGCR--9, pp:335-344
Remarks to and new proposals for the application of very CO2-rich natural gas from the NATUNA Gas Field in Indonesia
Barnert, H. (Forschungszentrum Juelich GmbH (Germany))
IAEA-TECDOC--923, pp:337-342
Status of design code work for metallic high temperature components
Bieniussa, K. (Gesellschaft fuer Reaktorsicherheit mbH, Koeln
(Germany)); Seehafer, H.J. (INTERATOM, Bergisch Gladbach
(Germany)); Over, H.H. (Kernforschungsanlage Juelich, IRW,
Juelich (Germany)); Hughes, P. (General Electric Co., CA
(United States))
IWGGCR--9, pp:345-362
Head-end processing of HTR fuel elements
Kaiser, G. (Kernforschungsanlage Juelich GmbH,
Projektleitung Hochtemperaturreaktor-Brennstoffkreislauf,
Juelich (Germany)); Barnert-Wiemer, H.; Hoogen, N.
(Kernforschungsanlage Juelich GmbH, Institut fuer Chemische
Technologie der Nuklearen Entsorgung, Juelich (Germany));
Wolf, J. (Kernforschungsanlage Juelich GmbH, Projektgruppe
JUPITER, Juelich (Germany))
IWGGCR--8, pp:357-368
Oxide films on austenitic HTR heat exchanger materials as a tritium permeation barrier
Buchkremer, H.P.; Hecker, R.; Jonas, H.; Leyers, H.J.;
Stoever, D. (Kernforschungsanlage Juelich GmbH, Juelich
(Germany))
IWGGCR--9, pp:363-376
Sorption of fission products on graphite and its influence on their
release behaviour in a pebble bed HTR under accident
conditions
Verfondern, K.; Hilpert, K.; Moormann, R. (KFA
Juelich (Germany))
IWGGCR--13, pp:371-384
The Klinger hot gas double axial valve
Kruschik, J. (Klinger Engineering, Wiener Neudorf (Austria));
Hiltgen, H. (INTERATOM GmbH, Bergisch-Gladbach
(Germany))
IWGGCR--9, pp:389-400
Status of the development of hot gas ducts for HTRs
Stehle, H.; Klas, E. (INTERATOM GmbH, Bergisch-Gladbach
(Germany))
IWGGCR--9, pp:413-428
Graphite and carbon/carbon components for hot gas ducts
Popp, G.; Gruber, U.; Boeder, H.; Janssen, K. (SIGRI
Elektrographit GmbH, Meitingen (Germany))
IWGGCR--9, pp:429-455
The HTR, applications, economics and environmental aspects
Barnert, H. (Nuclear Research Center Juelich, Institute for Reactor Development, Juelich (Germany)); Schad, M. (Lurgi GmbH, Frankfurt (Germany)); Candeli, H. (Interatom, Bensberg (Germany))
IAEA-TC--389.26, pp:450-465
Research on thermal insulation for hot gas ducts
Broeckerhoff, P. (Kernforschungsanlage Juelich GmbH, Institut
fuer Reaktorbauelemente, Juelich (Germany))
IWGGCR--9, pp:456-465
Facility for endurance tests of thermal insulations
Mauersberger, R. (Hochtemperatur-Reaktorbau GmbH, Juelich
(Germany))
IWGGCR--9, pp:466-476
Testing of high temperature components in the component testing facility (KVK)
Jansing, W. (INTERATOM GmbH, Bergisch-Gladbach
(Germany))
IWGGCR--9, pp:489-513
Operating experiences with heat-exchanging components of a semi-technical pilot plant for steam gasification of coal using heat from HTR
Kirchhoff, R.; Heek, K.H. van (Bergbau-Forschung GmbH,
Essen (Germany))
IWGGCR--9, pp:514-528
The test facility EVA II/ADAM II - Description and operational results
Harth, R.; Niessen, H.F.; Vau, V. (Kernforschungsanlage Juelich
GmbH, Juelich (Germany)); Merken, R. (Rheinbraun-Koeln
(Germany))
IWGGCR--9, pp:529-535
Modification of the AVR for high temperature process heat systems-demonstration
Barnert, H.; Kirch, N. (Kernforschungsanlage Juelich GmbH,
Juelich (Germany)); Ziermann, E. (Arbeitsgemeinschaft
Versuchsreaktor GmbH (Germany))
IWGGCR--9, pp:536-550
The materials programme for the high-temperature gas-cooled reactor in the Federal Republic of Germany: Status of the development of high-temperature materials, integrity concept, and design codes
Nickel, H. (Kernforschungsanlage Juelich GmbH, Juelich (Germany); RWTH Aachen (Germany)); Bodmann, E. (Hochtemperatur-Reaktorbau GmbH, Mannheim (Germany)); Seehafer, H.J. (Interatom GmbH, Bergisch-Gladbach (Germany))
IAEA-TC--389.26, pp:539-561
Gas metal arc narrow-gap welding of pressure vessels made from the nickel alloy 2.4663
Iversen, K. (INTERATOM GmbH, Bergisch-Gladbach
(Germany)); Palussek, A.
IWGGCR--9, pp:585-607
Forged hollows (alloy 617) for PNP-hot gas collectors
Hofmann, F. (Vereinigte Deutsche Metallwerke AG,
Geschaeftsbereich Nickel-Technologie, Werdohl (Germany))
IWGGCR--9, pp:608-619
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