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The way forward may be backwards for the HTRRIPPON, S. E.Modern power systems. 1983, Vol 3, Num 11, pp 33-34, issn 0260-7840Article

A new small HTGR power plant concept with inherently safe features ― an engineering and economic challengeMCDONALD, C. F; SONN, D. L.Proceedings of the American Power Conference. 1983, Vol 45, pp 818-825, issn 0097-2126Conference Paper

Internationales Interesse für den HochtemperaturreaktorSCHWARZ, D.VGB Kraftwerkstechnik. 1991, Vol 71, Num 12, pp 1096-1097, issn 0372-5715Article

High temperature molecular beam source reactorROTZOLL, G.International journal of chemical kinetics. 1984, Vol 16, Num 11, pp 1401-1426, issn 0538-8066Article

Seismic designIIGAKI, Kazuhiko; HANAWA, Satoshi.Nuclear engineering and design. 2004, Vol 233, Num 1-3, pp 59-70, issn 0029-5493, 12 p.Article

Enzymatic conversion of starch in twin-screw HTST-extruderHAKULIN, S; LINKO, Y.-Y; LINKO, P et al.Stärke. 1983, Vol 35, Num 12, pp 411-414, issn 0038-9056Article

Corrosion of mettalic materials in HTR-helium environmentsGRAHAM, L. W.Journal of nuclear materials. 1990, Vol 171, Num 1, pp 76-83, issn 0022-3115Article

Réacteurs à haute température = High temperature reactorsBASTIEN, Daniel.Techniques de l'ingénieur. Génie nucléaire. 1993, Vol BN2, Num B3190, pp B3190.1-B3190.19, issn 1762-875XArticle

Thermal response of a modular HTR under accident conditionsHAQUE, H; FELTES, W; WICKERT, M et al.Nuclear energy (1978). 1983, Vol 22, Num 3, pp 201-210, issn 0140-4067Article

Safety aspects of the combined httr/steam reforming complex for nuclear hyrogen productionVERFONDERN, Karl; NISHIHARA, Tetsuo.Progress in nuclear energy (New series). 2005, Vol 47, Num 1-4, pp 527-534, issn 0149-1970, 8 p.Conference Paper

After heat removal by a closed secondary cooler circuit on the example of the advanced high temperature reactor AHTR 500 with central graphite columnKLEIN, U; SINGH, J; BARNERT, H et al.Nuclear engineering and design. 1993, Vol 147, Num 1, pp 29-38, issn 0029-5493Article

Probabilistic method for evaluating reactivity margin of nuclear reactorsKANEKO, Y.Journal of Nuclear Science and Technology. 1984, Vol 21, Num 4, pp 308-314, issn 0022-3131Article

Status of the construction of the THTR-300 MW and the design of a 500 MW follow-on plantWITTCHOW, G; BAUST, E; SCHÖNING, J et al.Nuclear engineering and design. 1984, Vol 78, Num 2, pp 109-117, issn 0029-5493Article

Fonctionnement en régime quasi stationnaire, à haute température, d'un lit fluidisé de minibilles, en vue du revêtement, par des matériaux carbones, de substrats hétérogènes immergés en son sein = Quasi stationary high-temperature operation of a fluidized bed of small bells for carbon material wating coating of immersed heterogeneous substratesMOREAU, C; RANC, R.Journées européennes de fluidisation. 3. sd, pp 184-190Conference Paper

Alternative configurations for the QUADRISO fuel design conceptTALAMO, Alberto; POUCHON, Manuel A; VENNERI, Francesco et al.Journal of nuclear materials. 2009, Vol 383, Num 3, pp 264-266, issn 0022-3115, 3 p.Article

Graphite irradiation testing for HTR technology at the High Flux Reactor in PettenVREELING, J. A; WOUTERS, O; VAN DER LAAN, J. G et al.Journal of nuclear materials. 2008, Vol 381, Num 1-2, pp 68-75, issn 0022-3115, 8 p.Article

The safety of the HTR 500SCHNONING, J; WACHHOLZ, W.Nuclear engineering and design. 1985, Vol 85, Num 3, pp 285-291, issn 0029-5493Article

International aspects of high-temperature reactor developmentBALTHESEN, E; KUPITZ, J.Atomkernenergie, Kerntechnik. 1985, Vol 47, Num 3, pp 188-190, issn 0171-5747Article

Advantages of going modular in HTRsREUTLER, H; LOHNERT, G. H.Nuclear engineering and design. 1984, Vol 78, Num 2, pp 129-136, issn 0029-5493Article

Crushing strength of fuel kernels for high-temperature gas-cooled reactors 4AKABORI, M; SHIBA, K.Journal of Nuclear Science and Technology. 1984, Vol 21, Num 6, pp 66-475, issn 0022-3131Article

Zur passiven Nachwärmeabfuhr beim HTR mit dem Linerkühlsystem als Wärmesenke = Dissipation passive de la chaleur résiduelle d'un réacteur à haute température par le système de refroidissement du revêtement constituant un puits de chaleur = Passive afterheat removal in the HTR with the liner cooling system as a heat sinkREHM, W; JAHN, W; VERFONDERN, K et al.Berichte der Kernforschungsanlage Jülich. 1984, Num 1951, issn 0366-0885, 46 p.Serial Issue

Auslegung des inneren Graphitreflektors eines Hochtemperaturreaktors = Conception de réacteur interne en graphite d'un réacteur à haute température = Design of the inner graphite reflector of a high-temperature reactorTHEYMANN, W; DELLE, W; NICKEL, H et al.Berichte der Kernforschungsanlage Jülich. 1984, Num 1906, issn 0366-0885, 120 p.Serial Issue

Oxidation behaviour of an HTR fuel element matrix graphite in oxygen compared to a standard nuclear graphiteMOORMANN, Rainer; HINSSEN, Hans-Klemens; KÜHN, Kerstin et al.Nuclear engineering and design. 2004, Vol 227, Num 3, pp 281-284, issn 0029-5493, 4 p.Article

Sicherheit von Hochtemperaturreaktoren. Bericht über die KTG-Fachtagung am 19./20. 3.85 in der KFA Jülich = La sûreté des réacteurs à haute température. Rapport sur la réunion spécialisée KTG/KFA tenue à Julich en mars 1985 = The safety of high temperature reactors. Report about the KTG/KFA specialized meeting held in Jülich in March 1985REHM, W; UNGER, H.Atw. Atomwirtschaft, Atomtechnik. 1985, Vol 30, Num 11, pp 575-576, issn 0365-8414Article