H. WERLE

FZK investigations on ex-vessel melt behavior. (1998)

Kawamura, H. [Hrsg.]

Alsmeyer, H., Fieg, G., Tromm, W., Werle, H.

Brennelementtechnik, Kernauslegung, Reaktorbetrieb : Fachtagung der KTG-Fachgruppen 'Brennelemente' und 'Reaktorphysik und Berechnungsmethoden', Karlsruhe, 3.-4.Februar 1998

Spreading of the core melt on the spreading area of the EPR. (1998)

Ehrhard, P., Bunk, M., Fellmoser, F., Fieg, G., Foit, J.J., Huber, F., ...

ICONE-6 : Proc.of the 6th Internat.Conf.on Nuclear Engineering, San Diego, Calif., May 10-15, 1998

Determination of tritium profiles in first wall fusion reactor tiles and concepts for their detritiation. (1998)

Penzhorn, R.D., Bekris, N., Hellriegel, W., Knebel, D., Noppel, H.E., Nägele, W., ...

IEA Workshop on Tritium Experience in Large Tokamaks, Application to ITER, Princeton, N.J., March 16-18, 1998

Simulation experiments on the spreading behaviour of corium melts. (1998)

Fellmoser, F., Fieg, G., Massier, H., Schütz, W., Stegmaier, U., Werle, H.

Jahrestagung Kerntechnik 98, München, 26.-28.Mai 1998

Simulation experiments on the corium melt behaviour in the EPR reactor cavity: KAPOOL-tests. (1998)

Fellmoser, F., Fieg, G., Massier, H., Werle, H.

Jahrestagung Kerntechnik 98, München, 26.-28.Mai 1998

Influence of neutron damage on the tritium retention of ITER representative carbon fibre composites (CFC's). (1998)

Rolli, R., Werle, H., Wu, C.H.

4th Internat.Workshop on Tritium Effects in Plasma Facing Components, Santa Fe, N.M., May 14-15, 1998

Untersuchungen zum EPR-Konzept - KAPOOL- und KATS-Experimente. (1998)

Engel, G., Fellmoser, F., Fieg, G., Massier, H., Werle, H., Prothmann, N., ...

Projekt Nukleare Sicherheitsforschung. Jahresbericht 1997.

Spreading of the core melt on the spreading area of the EPR. (1998)

Ehrhard, P., Bunk, M., Foit, J.J., Müller, U., Siegel, U., Fellmoser, F., ...

Projekt Nukleare Sicherheitsforschung. Jahresbericht 1997.

Erosion products in disruption simulation experiments. (1998)

Safronov, V., Arkhipov, I., Arkhipov, N., Bakhtin, V., Barsuk, V., Kurkin, S., ...

Beaumont, B. [Hrsg.]

Long-time tritium release from neutron irradiated beryllium pebbles. (1998)

Metallographic investigation and mechanical behavior of beryllium pebbles at room temperature. (1997)

Beaumont, B. [Hrsg.]

Dalle Donne, M., Kaiser, E., Romer, O., Scaffidi-Argentina, F., Weimar, P., Werle, H.

Varandas, C. [Hrsg.]

Tritium release from neutron irradiated beryllium pebbles. (1997)

Evaluation of an advanced silicon doped CFC for plasma facing material. (1997)

Varandas, C. [Hrsg.]

Wu, C.H., Alessandrini, C., Bonal, P., Caso, A., Grote, H., Moormann, R., ...

Varandas, C. [Hrsg.]

Tritium distribution and release from neutron irradiated lithium orthosilicate pebbles. (1997)

Abramenkovs, A., Tiliks, J., Kizane, G., Werle, H., Tanaka, S.

Varandas, C. [Hrsg.]

Tritium release of beryllium pebbles from neutron-irradiated pure beryllium and mixed Li§4SiO§4/Beryllium beds. (1997)

Development work for lithium orthosilicate pebbles. (1997)

Casadio, S. [Hrsg.]

Dalle Donne, M., Piazza, G., Weisenburger, A., Werle, H., Geiler, V., Speit, B., ...

Varandas, C. [Hrsg.]

Simulation experiments on the spreading behaviour of molten core melts: KATS-3b and KATS-4. (1997)

Tritiumfreisetzung und Bestrahlungsverhalten von Brut- und Multiplier (Beryllium)-Materialien für das europäische heliumgekühlte 'Pebble Bed(HCPB)'-Blanket. (1997)

Wissenschaftliche Berichte, FZKA-5887 (März 97)

Dalle Donne, M., Scaffidi-Argentina, F., Werle, H.

Nachrichten - Forschungszentrum Karlsruhe, 29(1997) S.61-70

Simulation experiments on the spreading behaviour of core melts: KATS-6 (1-dim spreading of a low superheated iron melt into a dry channel). (1997)

Fieg, G., Huber, F., Werle, H.

Wissenschaftliche Berichte, FZKA-5956 (August 97)

Simulation experiments on the spreading behaviour of core melts: KATS-5 (1-dim spreading of an oxidic melt into a dry channel). (1997)

Untersuchungen zum EPR-Konzept. KATS- und KAPOOL-Experimente. (1997)

Wissenschaftliche Berichte, FZKA-5920 (Juni 97)

Engel, G., Fellmoser, F., Fieg, G., Massier, H., Werle, H., Huber, F., ...

Projekt Nukleare Sicherheitsforschung. Jahresbericht 1996.

Ex-vessel melt behaviour in the EPR. (1997)

Alsmeyer, H., Fellmoser, F., Fieg, G., Huber, F., Stegmaier, U., Tromm, W., ...

The European Pressurized Water Reactor EPR : KTG/SFEN Conf., Köln, October 19-21, 1997 Proc. Part II S.161-64

Critical assessment of beryllium pebbles response under neutron irradiation: mechanical performance and tritium release. (1997)

Scaffidi-Argentina, F., Dalle Donne, M., Werle, H.

8th Internat.Conf.on Fusion Reactor Materials, Sendai, J, October 26-31, 1997

Tritium release from EXOTIC-7 orthosilicate pebbles: effect of burnup and contact with beryllium during irradiation. (1997)

Simulation experiments on the spreading behaviour of core melts: KATS-7 (1-dim spreading of highly superheated iron and oxidic melts into a dry channel at low pouring rates). (1997)

6th Internat.Workshop on Ceramic Breeder Blanket Interactions, Mito, J, October 22-24, 1997

Fieg, G., Huber, F., Werle, H.

Wissenschaftliche Berichte, FZKA-6005 (November 97)

Beherrschung und Kühlung von Kernschmelzen ausserhalb des Druckbehälters. (1997)

Alsmeyer, H., Tromm, W., Albrecht, G., Huber, F., Stegmaier, U., Benz, H., ...

Nachrichten - Forschungszentrum Karlsruhe, 29(1997) S.327-35

Bestimmung der Tritiummenge in Graphit-Ziegeln von JET durch thermische Desorption. (1997)

Rolli, R., Werle, H.

Interner Bericht 31.02.02

Irradiation behavior of lithium orthosilicate and beryllium pebbles. (1996)

Weimar, P., Werle, H.

Yamawaki, M. [Hrsg.]

Tritium retention in neutron-irradiated carbon-based materials and beryllium. (1996)

Kwast, H., Werle, H., Wu, C.H.

7th Workshop on Carbon Materials, Stockholm, S, September 21-22, 1995

Overview on the results of the RCA project on molten core concrete interaction. (1996)

Alsmeyer, H., Kuczera, B., Werle, H., Bürger, M., Cognet, G., Cordfunke, E.H.P., ...

Van Goethem, G. [Hrsg.]

Untersuchungen zum EPR-Referenz-Konzept (KATS-Experimente). (1996)

Simulation experiments on the spreading behaviour of molten core melts. (1996)

Projekt Nukleare Sicherheitsforschung. Jahresbericht 1995.

Fieg, G., Huber, F., Werle, H., Wittmaack, R.

Proc.of the 1996 National Heat Transfer Conf., Houston, Tex., August 3-6, 1996 Vol. 9 S.121-30

Melt spreading and cooling experiments at Forschungszentrum Karlsruhe in view of the development of a core catcher system. (1996)

Scholtyssek, W., Alsmeyer, H., Werle, H.

Workshop on Severe Accident Research in Japan (SARJ), Tokyo, J, October 28-30, 1996

Recent results of melt spreading and cooling experiments at Forschungszentrum Karlsruhe - the KATS and COMET projects. (1996)

Scholtyssek, W., Alsmeyer, H., Werle, H.

Cooperative Severe Accident Research Program Meeting, Bethesda, Md., May 6-10, 1996

Tritium release and gamma activity of various lithium ceramics irradiated by fast and thermal neutrons (COMPLIMENT experiment). (1995)

Dörr, L., Schild, D., Werle, H.

KfK-5355 (Juni 94)

Tritium release processes from lithium orthosilicate ceramics. (1995)

Tiliks, J., Abramenkovs, A., Kizane, G., Grishmanov, V., Werle, H.

Herschbach, K. [Hrsg.]

Tritium release from neutron irradiated beryllium: kinetics, long-time annealing and effect of crack formation. (1995)

Studies for the staggered pans core catcher. (1995)

Proc.of the 2nd IEA Internat.Workshop on Beryllium Technology for Fusion, Jackson Lake Lodge, Wyo., September 6-8, 1995

Studies on core melt retention concepts for the EPR. (1995)

Nuclear Technology, 111(1995) S.331-40

Alsmeyer, H., Fieg, G., Huber, F., Tromm, W., Werle, H., Wittmaack, R.

Le Projet EPR : Actes de la Conf.Internat., Strasbourg, F, November 13-14, 1995 / SFEN/KTG

Untersuchungen zu H§2-Verbrennungsvorgängen. (1995)

Breitung, W., Hesselschwerdt, E., Massier, H., Möschke, M., Redlinger, R., Wilkening, H., ...

Projekt Nukleare Sicherheitsforschung. Jahresbericht 1994.

Untersuchungen zum EPR-Referenz-Konzept. (KATS-Experimente). (1995)

Activities at FZK in 1994/1995 for the investigation of hydrogen distribution and combustion phenomena in LWR core melt accidents (1995)

Projekt Nukleare Sicherheitsforschung. Jahresbericht 1994.

Breitung, W., Hesselschwerdt, E., Haytcher, E.A., Massier, H., Möschke, M., Redlinger, R., ...

Progress Report EU Contract Hydrogen Project FI3S-CT92-0003 (July 95)

Irradiation behaviour of ceramic breeder materials at high lithium-burnup. (1995)

Van Der Laan, J.G., Kwast, H., Conrad, R., May, R., Casadio, S., Roux, N., ...

7th Internat.Conf.on Fusion Reactor Materials (ICFRM-7), Obninsk, GUS, September 25-29, 1995

Molten corium/concrete interaction project. Final report. Executive summary, part C, part D. (1995)

Alsmeyer, H., Bürger, M., Cognet, G., Cordfunke, E.H.P., Fischer, M., Parozzi, F., ...

Luxembourg : Commision of the European Communities, 1995

Long-time tritium release from neutron-irradiated beryllium (SIBELIUS irradiation). (1995)

Werle, H., Dörr, L., Eberle, T., Lebkücher, J., Weisenburger, A.

Interner Bericht 31.06.10/01A (August 95)

The behaviour of ceramic breeder materials with respect to tritium release and pellet/pebble mechanical integrity. (1994)

Kwast, H., Conrad, R., May, R., Casadio, S., Roux, N., Werle, H.

6th Internat.Conf.on Fusion Reactor Materials, Stresa, I, September 27 - October 1, 1993

The effect of neutron irradiation on the trapping of tritium in carbon-based materials. (1994)

Kwast, H., Werle, H., Glugla, M., Wu, C.H., Federici, G.

6th Internat.Conf.on Fusion Reactor Materials, Stresa, I, September 27 - October 1, 1993

Influence of grain-size on tritium release from lithium orthosilicate (irradiation CORELLI-1) (1994)

Guenther, E., Wedemeyer, H., Werle, H.

Roux, N. [Hrsg.]

Long-time tritium release from irradiated beryllium (SIBELIUS irradiation). (1994)

Doerr, L., Eberle, T., Lebkücher, J., Werle, H.

Workshop on Beryllium for Fusion Applications, Karlsruhe, October 4-5, 1993

Neutron irradiation effects on the properties of carbon materials. (1994)

Wu, C.H., Bonal, J.P., Thiele, B., Tsotridis, G., Kwast, H., Werle, H., ...

6th Internat.Conf.on Fusion Reactor Materials, Stresa, I, September 27 - October 1, 1993

Untersuchungen zu Kernfänger-Konzepten. (1994)

Kernschmelzkühleinrichtungen für zukünftige DWR-Anlagen. (1994)

Sicherheitsorientierte LWR-Forschung. Jahresbericht 1993.

Alsmeyer, H., Werle, H.

Sammlung der Vorträge zum Statusbericht des Projektes Nukleare Sicherheitsforschung (PSF) vom 23.März 1994 im Kernforschungszentrum Karlsruhe.

Kernschmelzkühleinrichtungen für zukünftige DWR-Anlagen. (1994)

Alsmeyer, H., Werle, H.

KfK-Nachrichten, 26(1994) S.170-78

Studies for the staggered pans corecatcher. (1994)

European DEMO BOT solid breeder blanket. (1994)

ENC '94 : Internat.Nuclear Congress Atoms for Energy ; a Dialogue with the Industry's Young Generation on Nuclear's Future, Lyon, F, October 2-6, 1994

Dalle Donne, M., [Hrsg.], Albrecht, H., Boccaccini, L.V., Dammel, F., Fischer, U., ...

KfK-5429 (November 94)

Progress report for the commission of the European Communities reinforced concerted action on reactor safety containement project 'hydrogen detonation'. (1994)

Breitung, W., Möschke, M., Redlinger, R., Werle, H., Wolff, J., Forestier, A., ...

Rapport DMT/93-646

Experimente zur Schmelzenausbreitung (SIEMENS-Konzept): KATS-1 und KATS-2. (1994)

Release of neutron-generated tritium from beryllium. (1994)

Interner Bericht 32.21.04/04A (April 94)

Tritium release from beryllium irradiated in the SIBELIUS experiment. (1993)

Interner Bericht 31.06.02/P21A (Oktober 94)

The effect of purge gas composition on the release of tritium from ceramic breeder materials irradiated in EXOTIC-6. (1993)

Ferro, C. [Hrsg.]

Kwast, H., Conrad, R., May, R., Casadio, S., Roux, N., Werle, H.

Ferro, C. [Hrsg.]

Tritium release from lithium silicates. (1993)

Abramenkovs, A., Tiliks, J., Werle, H.

Ferro, C. [Hrsg.]

Radiolysis of solid blanket materials. (1993)

Tiliks, J., Kizane, G., Abramenkovs, A., Supe, A., Tiliks, J., Vasiljev, V., ...

Ferro, C. [Hrsg.]

Mechanical properties and dehydration of Li§4SiO§4 pebbles. (1993)

Schauer, V., Dalle Donne, M., Huber, R., Schmitt, B., Schumacher, G., Werle, H.

Ferro, C. [Hrsg.]

Studies for the staggered pans corecatcher. (1993)

Investigation of containment loads from hydrogen-air-steam detonations. (1993)

Proc.of the SMIRT 12 Post Conference Seminar 'Containment of Nuclear Reactors', Karlsruhe, August 23-24, 1993

Breitung, W., Hesselschwerdt, E., Moeschke, M., Redlinger, R., Werle, H.

Sicherheitsorientierte LWR-Forschung. Jahresbericht 1992.

Rueckhaltung der Kernschmelze in einer poroesen Struktur. (1993)

Inpile tritium release from ceramic breeder materials in TRIDEX experimens 1-6. (1992)

Sicherheitsorientierte LWR-Forschung. Jahresbericht 1992.

Krug, W., Bays, H.G., Juenemann, H., Krauthausen, W., Schmidt, F., Seferiadis, J., ...

Proc.of the 2nd Internat.Symp.on Fusion Nuclear Technology, Karlsruhe, June 2-7, 1991 Part B

Two core catcher concepts for innovative future PWR containments. (1992)

Kuczera, B., Alsmeyer, H., Fieg, G., Tromm, W., Werle, H.

Proc.of the Joint Internat.Meeting of the American Nuclear Society and the European Nuclear Society, Chicago, Ill., November 15-20, 1992

Investigation of hydrogen-deflagration/ -detonation. (1992)

Breitung, W., Redlinger, R., Werle, H., Moeschke, M.

Sicherheitsorientierte LWR-Forschung. Jahresbericht 1991.

Rueckhaltung der Kernschmelze in einer poroesen Struktur. (1992)

Freezing phenomena of ceramic alumina melts flowing in pin bundles. (1992)

Sicherheitsorientierte LWR-Forschung. Jahresbericht 1991.

Influence of grain-size and carbonate impurities on the tritium release from lithium orthosilicate. (1992)

Nuclear Technology, 99(1992) S.309-17

Wedemeyer, H., Werle, H., Guenther, E.

Proc.of the 5th Internat.Conf.on Fusion Reactor Materials (ICFRM-5), Clearwater, Fla., November 17-22, 1991

Tritium release of Li§4SiO§4, Li§2O and beryllium and chemical compatibility of beryllium with Li§4SiO§4, Li§2O and steel (SIBELIUS irradiation). (1992)

Dienst, W., Schild, D., Werle, H.

KfK-5109 (Dezember 92)

Research and development work for the lithium orthosilicate pebbles for the Karlsruhe ceramic breeder blanket. (1991)

Dalle Donne, M., Guenther, E., Schumacher, G., Sordon, G., Vollath, D., Wedemeyer, H., ...

Proc.of the 4th Internat.Conf.on Fusion Reactor Materials (ICFRM-4), Kyoto, J, December 4-8, 1989

Experimental evidence for tritium release-controlling processes in lithium silicates. (1991)

Breitung, W., Werle, H.

Proc.of the 4th Internat.Conf.on Fusion Reactor Materials (ICFRM-4), Kyoto, J, December 4-8, 1989

Fabrication of grain-size controlled lithium orthosilicate. (1991)

Wedemeyer, H., Ritzhaupt-Kleissl, H.J., Guenther, E., Werle, H.

Keen, B.E. [Hrsg.]

Tritium release from low- and high-density lithium meta- and orthosilicate (irradiation DELICE 2). (1991)

Breitung, W., Elbel, H., Wedemeyer, H., Werle, H.

Keen, B.E. [Hrsg.]

In-pile tritium release from lithium ceramics and influence of surface processes. (1991)

Briec, M., Kopasz, J., Casadio, S., Werle, H.

Keen, B.E. [Hrsg.]

Comparison of the tritium residence times of various ceramic breeder materials irradiated in EXOTIC experiments 4 and 5. (1991)

Kwast, W., Conrad, R., Preston, S.D., Verstappen, G., Roux, N., Casadio, S., ...

Keen, B.E. [Hrsg.]

Tritium release from lithium orthosilicate and metazirconate: influence of purge gas additives and sample impurities, order of release reaction. (1991)

Breitung, W., Werle, H., Krug, W.

Werle, H. [Hrsg.]

Status report KfK contribution to the development of DEMO-relevant test blankets for NET/ITER. Part 2: BOT helium cooled solid breeder blanket. Vol. 2: detailed version. (1991)

Dalle Donne, M., [Hrsg.], Adelhelm, C., Baschek, H.D., Boccaccini, L.V., Bogusch, E., ...

KfK-4929 (Oktober 91)

Status report KfK contribution to the development of DEMO-relevant test blankets for NET/ITER. Part 2: BOT helium cooled solid breeder blanket. Vol. 1: Summary. (1991)

Dalle Donne, M., [Hrsg.], Adelhelm, C., Baschek, H.D., Boccaccini, L.V., Bogusch, E., ...

KfK-4928 (Oktober 91)

Doped lithium orthosilicate, preparation and properties. (1990)

Vollath, D., Wedemeyer, H., Zimmermann, H., Werle, H.

4th Internat.Conf.on Fusion Reactor Materials, Kyoto, J, December 4-8, 1989

Penetration and freezing phenomena of ceramic melts into pin-bundles. (1990)

Fieg, G., Moeschke, M., Schub, I., Werle, H.

Proc.of the 1990 Internat.Fast Reactor Safety Meeting, Snowbird, Utah, August 12-16, 1990

Tritium release from lithium silicate. (1989)

Breitung, W., Briec, M., Werle, H.

Proc.of the 1st Internat.Symp.on Fusion Nuclear Technology, Tokyo, J, April 10-19, 1988 Part A

Preparation, phase relationships and first irradiation results of lithium orthosilicate doped with Al`3`+- and P`5`+-ions. (1989)

Skokan, A., Vollath, D., Wedemeyer, H., Guenther, E., Werle, H.

Van Ingen, A.M. [Hrsg.]

Bestrahlung von keramischen Brutmaterialien fuer Fusionsreaktor-Blankets im FRJ-2. (1989)

Krug, W., Bays, H.G., Juenemann, H., Krauthausen, W., Schmidt, F., Seferiadis, J., ...

Jahrestagung Kerntechnik 89. Duesseldorf, 9.-11.Mai 1989

Comparison of tritium release from lithium silicates with that predicted by diffusion theory. (1989)

Werle, H., Breitung, W., Schumacher, G.

Fabrication and Properties of Lithium Ceramics : Proc.of the Symp.during the 89th Annual Meeting and Exposition of the American Ceramic Society, Pittsburgh, Pa., April 26-30, 1987

Tritiuminventar in keramischen Blankets. (1989)

Breitung, W., Werle, H.

KfK-Nachrichten, 21(1989) S.265-72

Tritium release from lithium silicate, measurements and modeling. (1989)

Trials to induce neutron emission from a titanium-deuterium system. (1989)

Workshop on Fusion Reactor Fuel - Material Interaction, Tokyo, J, December 11-12, 1989

Werle, H., Fieg, G., Lebkuecher, J., Moeschke, M.

Fusion Technology, 16(1989) S.391-96

Out of pile tritium extraction from lithium silicate. (1988)

Breitung, W., Elbel, H., Lebkuecher, J., Schumacher, G., Werle, H.

Proc.of the 3rd Internat.Conf.on Fusion Reactor Materials, Karlsruhe, October 4-8, 1987 Part A

The LISA-2 experiment: in-situ tritium release from lithium orthosilicate (Li§4SiO§4). (1988)

Werle, H., Breitung, W., Briec, M., Clemmer, R.G., Elbel, H., Haefner, H.E., ...

Proc.of the 3rd Internat.Conf.on Fusion Reactor Materials, Karlsruhe, October 4-8, 1987 Part A

In-pile tritium extraction from samples of lithium aluminate. (1988)

Briec, M., Abassin, J.J., Masson, M., Roth, E., Sciers, P., Werle, H.

Proc.of the 3rd Internat.Conf.on Fusion Reactor Materials, Karlsruhe, October 4-8, 1987 Part A

The LISA1 experiment: in-situ tritium release investigations. (1987)

Werle, H., Abassin, J.J., Briec, M., Clemmer, R.G., Elbel, H., Haefner, H.E., ...

2nd Internat.Conf.on Fusion Reactor Materials (ICFRM-2), Chicago, Ill., April 13-17, 1986 Journal of Nuclear Materials, 141-143(1986) S.321-26

Cooling of particulate core debris beds. (1987)

Freezing phenomena of flowing melts in non-melting and melting tubes. (1987)

Science and Technology of Fast Reactor Safety : Proc.of an Internat.Conf.,

Fieg, G., Henkel, P.R., Moeschke, M., Schub, I., Werle, H.

Science and Technology of Fast Reactor Safety : Proc.of an Internat.Conf.,

In and out of pile tritium extraction from samples of tritium aluminates. (1987)

Briec, M., Botter, F., Abassin, J.J., Benoit, R., Chenebault, P., Masson, M., ...

2nd Internat.Conf.on Fusion Reactor Materials (ICFRM-2), Chicago, Ill., April 13-17, 1986

Tritium recovery from a breeder material gamma lithium aluminate. (1987)

Roth, E., Botter, F., Briec, M., Rostaing, M., Werle, H., Clemmer, R.G.

2nd Internat.Conf.on Fusion Reactor Materials (ICFRM-2), Chicago, Ill., April 13-17, 1986

Comparison of tritium release from lithium-silicates with predictions of diffusion theory. (1987)

Werle, H., Breitung, W., Schumacher, G.

Hastings, I.J. [Hrsg.]

Untersuchungen zum Ausfrierverhalten geschmolzener Kernmaterialien. (1987)

Fieg, G., Moeschke, M., Ohnemus, J., Werle, H.

KfK-Nachrichten, 19(1987) S.44-49

Phase relationship, preparation, and first irradiation results of lithium orthosilicate doped with Al`3`+- and P`5`+-ions. (1987)

Skokan, A., Vollath, D., Wedemeyer, H., Guenther, E., Werle, H.

3rd Internat.Conf.on Fusion Reactor Materials, Karlsruhe, October 4-8, 1987

Extended dryout and rewetting of small particle core debris. (1986)

Penetration of a heated pool into a melting miscible substrate. (1986)

Dhir, V.K. [Hrsg.]

Eck, G., Werle, H.

Dhir, V.K. [Hrsg.]

The LISA-I and Trio in-pile tests. (1986)

Clemmer, R.G., Werle, H.

Internat.Symp.on Fusion Reactor Blanket and Fuel Cycle Technology, Tokai-Mura, J, October 27-29, 1986

Extended dryout and rewetting of particulate core debris beds. (1985)

Experimental studies of penetration of a hot liquid pool into a melting miscible substrate. (1984)

Bork, G.; Rininsland, H. [Hrsg.]

Eck, G., Werle, H.

Nuclear Technology, 64(1984) S.275-89

Cooling of debris beds. (1984)

Heat transfer in particulate beds. (1983)

Nuclear Technology, 65(1984) S.67-86

Barleon, L., Werle, H., Lipinski, R.J.

LMFBR Safety: Proc.of the Topical Meeting, Lyon, F, July 19-23, 1982

Further work on sodium borates as sacrificial materials for a core-catcher. (1983)

Dalle Donne, M., Dorner, S., Roth, A., Werle, H.

LMFBR Safety: Proc.of the Topical Meeting, Lyon, F, July 19-23, 1982

Freezing of aluminium oxide and iron flowing upward in circular quartz glass tubes. (1983)

Kuhn, D., Moeschke, M., Werle, H.

KfK-3592 (Oktober 83)

Verhalten von Kernschmelzen und Partikelbetten bei schweren Unfaellen. (1983)

Barleon, L., Feuerstein, H., Perinic, D., Kuhn, D., Werle, H.

KfK-Nachrichten, 15(1983) S.250-53

Dependence of dryout heat flux on particle diameter and bed height and effects of stratification and bed reconfiguration. (1982)

Bottom cooling of particulate debris beds. (1982)

Mueller, U.; Guenter, G. [Hrsg.]

Enhancement of heat transfer between two horizontal liquid layers by gas injection at the bottom. (1982)

Mueller, U.; Guenter, G. [Hrsg.]

Some experiments on penetration of molten steel through stainless steel tubes. (1982)

Nuclear Technology, 59(1982) S.160-64

Kuhn, D., Moeschke, M., Werle, H.

10th Meeting of the Liquid Metal Boiling Working Group, Karlsruhe, October 27-29, 1982

Heat transfer in particulate beds. (1982)

Untersuchungen zum Dryout von Partikelschuettbetten mit adiabatem und gekuehltem Boden. (1981)

10th Meeting of the Liquid Metal Boiling Working Group, Karlsruhe, October 27-29, 1982

Dependence of debris bed dryout heat flux on particle diameter. (1981)

Jahrestagung Kerntechnik 81. Reaktortagung 1981. Duesseldorf, 24.-26.Maerz 1981.

Enhancement of heat transfer between two horizontal liquid layers by gas injection at the bottom. (1981)

Godlewski, N.Z. [Hrsg.]

Dependence of dryout heat flux on particle diameter for volume- and bottom-heated debris beds. (1981)

KfK-3223 (Oktober 81)

Debris bed investigations with adiabatic and cooled bottom. (1980)

KfK-3138 (November 81)

Laboratory studies of the meltfront propagation in a borax core-catcher. (1980)

Kottowski, H.M. [Hrsg.]

Dalle Donne, M., Werle, H.

KfK-3021 (August 80)

Further work for the GCFR borax core-catcher. (1979)

Dalle Donne, M., Dorner, S., Fieg, G., Schumacher, G., Werle, H.

Specialist Meeting on Gas-cooled Fast Reactor Safety and Associated Design Features, Brussels (Belgium), March 13-15, 1979

Development work for fast reactor core-catchers on the basis of sodium borates. (1979)

Dalle Donne, M., Dorner, S., Fieg, G., Schumacher, G., Werle, H.

Fast Reactor Safety Technology. Proc.of the Internat.Meeting. Seattle, Wash., August 19-23, 1979. La Grange Park,Ill.: American Nuclear Soc.1979. Vol.I, S.400-11

Experimental investigations of heat transfer in pools. (1979)

Fieg, G., Werle, H.

Fast Reactor Safety Technology. Proc.of the Internat.Meeting. Seattle, Wash., August 19-23, 1979. La Grange Park,Ill.: American Nuclear Soc.1979. Vol.I, S.346-55

Einfluss eines Gasstroms auf den Waermeuebergang zwischen zwei Fluessigkeitsschichten. (1979)

Modellexperimente zur Thermodynamik von Kernschmelzen. (1978)

In: Projekt Nukleare Sicherheit. Halbjahresbericht 1978/2. KfK-2750 (Oktober 79) S.4300/79-4300/82

Fieg, G., Werle, H.

Reaktortagung, Hannover, 4.-7.April 1978, Deutsches Atomforum e.V., Kerntechnische Ges.im Dt.Atomforum e.V. Leopoldshafen 1978: ZAED. S.266-69

Neutron spectra and tritium production measurements in a lithium sphere to check fusion reactor blanket calculations. (1978)

Bachmann, H., Fritscher, U., Kappler, F., Rusch, D., Werle, H., Wiese, H.W.

Nuclear Science and Engineering, 67(1978) S.74-84

Measurement and calculation of californium-252 fission neutron-induced gamma fields in iron. (1978)

Jiang, S.H., Werle, H.

Nuclear Science and Engineering, 66(1978) S.354-62

Untersuchungen zu Kernschmelzen. (1978)

Alsmeyer, H., Barleon, L., Dorner, S., Fieg, G., Goetzmann, O., Guenther, C., ...

KfK-Nachrichten, 10(1978) No 3/4

Experimental investigation of heat transfer between two horizontal liquid layers with gas injection. (1978)

Modellexperimente zum Kernschmelzen. (1978)

PAHR Information Exchange Meeting, Ispra, Italy, October 10-12, 1978

LMFBR post accident heat removal testing needs and conceptual design of a test facility. (1977)

In: Projekt Nukleare Sicherheit. Halbjahresbericht 1978/1. KfK-2700 (November 78) S.4300/77-4300/85

Kleefeldt, K., Kuechle, M., Royl, P., Werle, H., [Hrsg.], Boenisch, G., ...

KFK-Ext.08/76-04 (Maerz 77)

Untersuchungen zur Kuehlung von Kernschmelzen. (1977)

Fieg, G., Werle, H.

In: Projekt Schneller Brueter. 4.Vierteljahresbericht 1976. KFK-1276/4 (April 77) S.123/32-42

Messung und Berechnung des durch Spaltneutronen in Eisen induzierten #g-Feldes. (1977)

Jiang, S.H., Werle, H.

Reaktortagung, Mannheim, 29.Maerz - 1.April 1977, Deutsches Atomforum e.V. Kerntechnische Ges.im Dt.Atomforum e.V. Leopoldshafen 1977: ZAED. S.99-102

Modellexperiment zum Fusionsreaktor-Blanket. (1977)

Fritscher, U., Kappler, F., Rusch, D., Werle, H., Wiese, H.W.

Reaktortagung, Mannheim, 29.Maerz - 1.April 1977, Deutsches Atomforum e.V. Kerntechnische Ges.im Dt.Atomforum e.V. Leopoldshafen 1977: ZAED. S.997-1000

Measurement and calculation of `2`5`2Cf-fission neutron induced gamma fields in iron. (1977)

Jiang, S.H., Werle, H.

In: Projekt Schneller Brueter. 2.Vierteljahresbericht 1977.

Heat transfer measurements from internally heated liquids enclosed by nonmelting and melting boundaries. (1977)

Fieg, G., Werle, H., Mueller, U.

Annual Post-Accident Heat Removal Information Exchange Meeting, Argonne, Ill., November 2-4, 1977

Determination of Neutron Spectra and Cross-section Sensitivity of Tritium Production in a Lithium Sphere. (1976)

Fritscher, U., Kappler, F., Rusch, D., Werle, H., Wiese, H.W.

Proc. of the 9. Symposium on fusion technology, Garmisch-Partenkirchen, June 14-18, 1976. Oxford[usw.]: Pergamon Pr. 1976. S. 583-88

Considerations on a PAHR test facility. (1976)

Boenisch, G., Groetzbach, G., Heinzel, V., Kleefeldt, K., Kuechle, M., Mueller, R.A., ...

Internat. Meeting on Fast Reactor Safety and Related Physics, Chicago, Ill., October 5-8, 1976

Untersuchungen zur Kuehlung von Kernschmelzen. (1976)

Fieg, G., Guenther, C., Boenisch, G., Groetzbach, G., Kleefeldt, K., Mueller, R.A., ...

In: Projekt Schneller Brueter. 2.Vierteljahresbericht 1976.

Laboratory experiments to check cooling tower computer models. (1976)

Einmaterial - Experimente in Kugelgeometrie zum Vergleich gemessener und gerechneter Neutronenspektren. (1975)

Nuclear Technology, 28(1976) S. 172

Bluhm, H., Fieg, G., Kappler, F., Kuhn, D., Lalovic, M., Rusch, D., ...

Reaktortagung, Nuernberg, 8.-11. April 1975, Deutsches Atomforum e.V., Kerntechnische Ges.im Dt.Atomforum e.V. Leopoldshafen 1975: ZAED. S.285-88

Spektrometrie schneller Neutronen in der Reaktorphysik und Kerntechnik. (1975)

Bluhm, H., Fieg, G., Kappler, F., Rusch, D., Werle, H.

Beitraege zur Kerntechnik. Karl Wirtz gewidmet zum 65.Geburtstag

`2`5`2Cf fission neutron spectrum and use of `2`5`2Cf sources to examine neutron-cross sections by neutron spectrum measurements. (1975)

Design Characteristics of the CABRI Neutron Hodoscope. (1975)

IAEA Seminar on the Uses of Cf-252 in Teaching and Research, Karlsruhe, April 14-18, 1975

Bluhm, H., Boehnel, K., Kuechle, M., Werle, H.

Information Meeting on Fuel and Clad Motion Diagnostics for LMFBR Safety Test Facilities, Albuquerque, N.M., November 11-12, 1975

Neutron Leakage Spectra from Iron Spheres with a `2`5`2Cf Neutron Source in the Centre. (1975)

Werle, H., Bluhm, H., Fieg, G., Kappler, F., Kuhn, D., Lalovic, M.

Specialists' Meeting on Sensitivity Studies and Shielding Benchmarks, Paris, October 7-10, 1975

Messung und Berechnung der Neutronenleckage - Spektren von Eisenkugeln mit einer `2`5`2Cf-Quelle im Zentrum. (1975)

Werle, H., Bluhm, H., Fieg, G., Kappler, F., Kuhn, D., Lalovic, M.

KFK-2219 (November 75)

Neutron Spectrometry Techniques for the Energy Region 0.1 to 10 MeV. (1975)

Werle, H., Bluhm, H., Fieg, G.

1.Internat.Symposium on Reactor Dosimetry: Developments and Standardization, Petten, September 22-25, 1975

Determination of Neutron Spectra in a Lithium Sphere. (1974)

Bluhm, H., Kappler, F., Kuehn, D., Rusch, D., Werle, H., Wiese, H.W.

8.Symposium on Fusion Technology, Noordwijkerhout/Netherlands, June 17-21, 1974

Vergleich verschiedener Neutronenspektrometer fuer den Energiebereich 0,1-10 MeV. (1974)

Bluhm, H., Korthaus, E., Rusch, D., Werle, H.

Symposium ueber Neutronendosimetrie in Biologie und Medizin, Neuherberg, 30.September - 4.Oktober 1974

Untersuchungen zur Nachbildung von Kuehlturmfahnen in Modellexperimenten. (1974)

The Neutron Spectrum of a `2`2`7Ac-Be (#a,n) Source. (1973)

KFK-1984 (August 74)

Werle, H., Geiger, K.W., Zwan, L.van Der

International Journal of Applied Radiation and Isotopes, 24(1973) S.165-69

The Neutron Continuum from the `9Be + #a Reaction. (1973)

Werle, H., Zwan, L.van Der, Geiger, K.W.

Zeitschrift fuer Physik, 259(1973) S.275-84

Untersuchung von Uran- und Eisen-Wirkungsquerschnitten mittels Neutronenspektrumsmessungen. (1973)

Bluhm, H., Rusch, D., Stancu, M., Werle, H., Wattecamps, E.

Atomwirtschaft-Atomtechnik, 18(1973) S.175-76

(n,#g)-Cross-Section Measurements of `9`9Tc, Eu, Sm and Fe in the Energy Range 1 eV to 50 keV with a Slowing-Down Time Spectrometer. (1973)

Chou, J.C., Werle, H.

Journal of Nuclear Energy, 27(1973) S.811-23

Measurements of Fast Neutron Spectra in Iron, Uranium and Sodium-Iron Assemblies. (1973)

Wattecamps, E., Pieroni, N., Kappler, F., Rusch, D., Schmidt, A., Werle, H.

International Symposium on Physics of Fast Reactors, Tokyo, October 16-23, 1973

Messungen der Spaltneutronenspektren von U-235, Pu-239 und Cf-252. (1972)

Werle, H., Bluhm, H.J.

Atomwirtschaft-Atomtechnik, 4(1972) S.201-2

Neutron Spectrometry with Proton-Recoil Proportional Counters in the Energy Region up to 10 MeV. (1972)

Bestimmung der #g-Heizung in schnellen Reaktoren mit Radiophotolumineszenzglaesern. (1972)

Nuclear Instruments and Methods, 99(1972) S.295-300