W. Scholtyssek

SARNET: SUSTAINABLE INTEGRATION OF EU RESEARCH ON SEVERE ACCIDENT PHENOMENOLOGY AND MANAGEMENT (2008)

J. C. Micaelli, M. Schwarz, V. Teschendorff, G. Cognet, W. Scholtyssek, R. Sehgal, ...

In spite of the accomplishments reached in severe accident research, thanks notably to the EU projects carried out during previous Framework Programmes, a limited number of specific items remain...

Severe fuel damage experiments performed in the QUENCH facility with 21-rod bundles of LWR-type. (2007)

Sepold, L., Hering, W., Schanz, G., Scholtyssek, W., Steinbrück, M., Stuckert, J.

Nuclear Engineering and Design, 237(2007) S.2157-64

Status of the QUENCH program at FZK. (2007)

Steinbrück, M., Große, M., Stegmaier, U., Steinbock, L., Heck, M., Laier, J., ...

Steinbrück, M. [Hrsg.]

Severe fuel damage experiments performed in the QUENCH facility with 21-rod bundles of LWR-type. (2006)

Sepold, L., Hering, W., Schanz, G., Scholtyssek, W., Steinbrück, M., Stuckert, J.

Technical Meeting on Severe Accident and Accident Management for Nuclear Power Plants, Tokyo, J, March 14-16, 2006

Sicherheitsforschung für Kernreaktoren. (2006)

Scholtyssek, W., Tromm, W.

Nachrichten - Forschungszentrum Karlsruhe, 38(2006) S.28-32

Integral large scale experiments on hydrogen combustion for severe accident code validation (HYCOM). (2005)

Scholtyssek, W., Bielert, K., Dorofeev, S., Breitung, W., Kotchourko, A., Kuznetsov, M., ...

FISA-2003 : EU Research in Reactor Safety ; Conclusion Symp.on Shared-Cost and Concerted Actions, Luxembourg, L, November 10-13, 2003

Integral large scale experiments on hydrogen combustion for severe accident code validation-HYCOM. (2005)

Breitung, W., Dorofeev, S., Kotchourko, A., Redlinger, R., Scholtyssek, W., Bentaib, A., ...

Nuclear Engineering and Design, 235(2005) S.253-70

Overview of the Quench program. Hydrogen generation during core reflooding. (2005)

Stuckert, J., Schanz, G., Sepold, L., Stegmaier, U., Steinbock, L., Steinbrück, M., ...

1st Annual SARNET-WP9 Review Meeting (Network of Excellence on Severe Accidents Research), Köln, February 16, 2005

Status of the QUENCH program at FZK. (2005)

Große, M., Stegmaier, U., Steinbock, L., Steinbrück, M., Heck, M., Laier, J., ...

Steinbrück, M. [Hrsg.]

Status of the QUENCH program. (2004)

Hering, W., Homann, C., Meier, A., Stegmaier, U., Steinbock, L., Steinbrück, M., ...

9th Internat.QUENCH Workshop, Karlsruhe, October 13-15, 2003

Verbleibende Fragestellungen zukünftiger Forschungsarbeiten. (2004)

Scholtyssek, W., Rohde, J.

Fortschritte bei der Beherrschung und Begrenzung der Folgen auslegungsüberschreitender Ereignisse : Bericht vom KTG-Fachtag der Fachgruppen Reaktorsicherheit und Thermo- und Fluiddynamik, Karlsruhe,...

Großexperimente im Forschungszentrum Karlsruhe zur LWR Sicherheit. (2004)

Alsmeyer, H., Eppinger, B., Hofmann, P., Kuczera, B., Scholtyssek, W., Schütz, W., ...

ATW - International Journal for Nuclear Power, 49(2004) S.328-32

ECOSTAR. Final report. (2004)

Alsmeyer, H., Albrecht, G., Meyer, L., Scholtyssek, W., Häfner, W., Journeau, C., ...

Contract FIKS-CT1999-00003. Ex-Vessel Core Melt Stabilization Research

Overview of the QUENCH program at FZK. (2004)

Hering, W., Homann, C., Steinbrück, M., Meier, A., Stegmaier, U., Steinbock, L., ...

Spring Meeting of the Cooperative Severe Accident Research Programme (CSARP), Arlington, Va., May 3-4, 2004

Status of the QUENCH program at FZK. (2004)

Meier, A., Stegmaier, U., Steinbock, L., Steinbrück, M., Heck, M., Laier, J., ...

10th Internat.QUENCH Workshop, Karlsruhe, October 26-28, 2004

Post-test examination of QUENCH-09 bundle degradation; comparison towards phenomena to be considered. (2004)

Meier, A., Stegmaier, U., Steinbock, L., Steinbrück, M., Heck, M., Laier, J., ...

Phebus Fission Product Test 23. Bundle Interpretation Circle (BIC) Meeting, Aix-en-Provence, F, November 4, 2004

Application and assessment of hydrogen combustion models. (2003)

Baraldi, D., Heitsch, M., Eyink, J., Movahed, M.A., Dorofeev, S., Kotchourko, A., ...

NURETH-10 : The 10th Internat.Topical Meeting on Nuclear Reactor Thermal Hydraulics, Seoul, Korea, October 5-11, 2003

Fortschritte bei der Beherrschung und Begrenzung der Folgen auslegungsüberschreitender Ereignisse. (2003)

Scholtyssek, W., Fabian, H., [Hrsg.]

Wissenschaftliche Berichte, FZKA-6935 (Dezember 2003)

Integral large scale experiments on hydrogen combustion for severe accident code validation HYCOM. (2002)

Bielert, U., Breitung, W., Burgeth, B., Kotchourko, A., Scholtyssek, W., Pailhories, P., ...

Van Goethem, G. [Hrsg.]

Large scale experiments for validation of hydrogen combustion models and criteria. (2002)

Bielert, U., Breitung, W., Burgeth, B., Dorofeev, S., Kotchourko, A., Scholtyssek, W., ...

Jahrestagung Kerntechnik 2002, Stuttgart, 14.-16.Mai 2002

Severe accident related research and development at Forschungszentrum Karlsruhe for present and future needs. (2002)

Scholtyssek, W., Heusener, G., Hofmann, F., Plitz, H.

Nuclear Technology, 139(2002) S.10-20

Multidimensional simulation of hydrogen distribution and turbulent combustion in severe accidents. (2002)

Bielert, U., [Hrsg.], Bielert, U., Kotchourko, A., Veser, A., Breitung, W., ...

Wissenschaftliche Berichte, FZKA-6696 (August 2002)

Multidimensional simulation of hydrogen distribution and turbulent combustion in severe accidents. (2001)

Bielert, U., Breitung, W., Kotchourko, A., Royl, P., Scholtyssek, W., Veser, A., ...

Van Goethem, G. [Hrsg.]

Severe accident related R&D at Forschungszentrum Karlsruhe. (2000)

Heusener, G., Hofmann, F., Plitz, H., Scholtyssek, W.

Annual Meeting of the American Nuclear Society, San Diego, Calif., June 4-8, 2000

Research on hydrogen risk mitigation resulting from hypothetical severe accident. (2000)

Eyink, J., Fischer, K., Heitsch, M., Rehm, W., Scholtyssek, W.

Atomwirtschaft-Atomtechnik, 45(2000) S.740-49

Experimental program to quantify the effects of severe accidents for PWR design. (1999)

Plitz, H., Hofmann, F., Scholtyssek, W.

Chang, S.P. [Hrsg.]

Multi-dimensional simulation of hydrogen distribution and combustion in severe accident. (1999)

Bielert, U., Kotchourko, A., Veser, A., Breitung, W., Royl, P., Scholtyssek, W., ...

FI4S-CT-95-0001 (October 99)

Assessment of the severe accident mitigation features of the European pressurized water reactor by cooperative research and development. (1999)

Eglin, W., Krugmann, U., Weisshäuptl, H.A., Scholtyssek, W.

Nuclear Technology, 126(1999) S.143-52

Investigation of ex-vessel corium melt behavior in support of core catcher development. (1998)

Scholtyssek, W.

Internat.Topical Meeting on Safety of Nuclear Power Plants (TOPSAFE '98), Valencia, E, April 15-17, 1998

Reactive flow simulation in complex 3D geometries using the COM3D code. (1998)

Breitung, W., Kotchourko, A., Veser, A., Scholtyssek, W.

Severe Accident Research in Japan (SARJ), Tokyo, J, November 4-6, 1998

Progress in LWR severe accident research at the FZK. (1998)

Heusener, G., Scholtyssek, W.

Severe Accident Research in Japan (SARJ), Tokyo, J, November 4-6, 1998

R and D at FZK to minimize energetic threats to containments of future reactors. (1998)

Scholtyssek, W.

ENC '98 : World Nuclear Congress, Nice, F, October 25-28, 1998

Bewertung des COMET-Corecatcher-Konzepts mit Hilfe des Codes CONTAIN. (1997)

Baumann, W., Scholtyssek, W.

Projekt Nukleare Sicherheitsforschung. Jahresbericht 1996.

Multidimensional simulation of hydrogen distribution and turbulent combustion in severe accidents. (1997)

Breitung, W., Royl, P., Scholtyssek, W., Armand, P., Huld, T., Klenk, B.

FISA-97 Symp.on EU Research on Severe Accidents, Luxembourg, L, November 17-19, 1997

Research at Forschungszentrum Karlsruhe in view of hydrogen and steam-explosion energetic threats to containment. (1996)

Scholtyssek, W., Hofmann, F., Plitz, H.

Internat.Conf.on Nuclear Containment, Cambridge, GB, September 23-25, 1996

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

Source term aspects associated with future PWR containment systems. (1995)

Kuczera, B., Kessler, G., Ehrhardt, J., Scholtyssek, W.

3rd Internat.Conf.on Containment Design and Operation, Toronto, CDN, October 19-21, 1994 Conf.Proc. Vol. 1

The release code package REVOLS/RENONS for fission product release from a liquid sodium pool into an inert gas atmosphere. (1995)

Starflinger, J., Koch, M.K., Brockmeier, U., Schütz, W., Scholtyssek, W., Unger, H.

KfK-5426 (Dezember 94)

Confinement of the radiological source term during beyond-design-basis events in future pressurized water reactors. (1995)

Kessler, G., Kuczera, B., Ehrhardt, J., Henneges, G., Scholtyssek, W., Wiese, H.W.

Nuclear Technology, 111(1995) S.305-18

Long-term containment thermal-hydraulic loads in pressurized water reactor core-melt accidents. (1995)

Scholtyssek, W.

Nuclear Technology, 111(1995) S.319-30

CONTAIN-Rechnungen. (1995)

Scholtyssek, W.

Projekt Nukleare Sicherheitsforschung. Jahresbericht 1994.

Recent results on hydrogen distribution and combustion research at the Forschungszentrum Karlsruhe. (1995)

Breitung, W., Schmuck, P., Royl, P., Sengpiel, W., Scholtyssek, W.

CSARP Meeting, Bethesda, Md., May 1-5, 1995

Overview on hydrogen research at Forschungszentrum Karlsruhe. (1995)

Breitung, W., Royl, P., Scholtyssek, W.

Hydrogen Combustion Working Group Meeting, Tokyo, J, December 7-8, 1995

Improved containment concept for future large LWR's. (1994)

Alsmeyer, H., Breitung, W., Erbacher, F.J., Goeller, B., Hennies, H.H., Jacobs, H., ...

Technology Responses to Global Environmental Challenges : Energy Collaboration for the 21st Century, IEA Internat.Conf., Kyoto, J, November 6-8, 1991 Conf.Proc. S.471-89

Sodium spray and jet fire model development within the CONTAIN-LMR code. (1994)

Scholtyssek, W., Murata, K.K.

Proc.of the Internat.Topical Meeting on Advanced Reactors Safety, Pittsburgh, Pa., April 17-21, 1994 Vol. 2 S.1029-37

Source term analysis of a core disruptive severe accident in a commercial liquid metal cooled reactor using the codes SIMMER-II and CONTAIN. (1994)

Scholtyssek, W., Maschek, W.

Proc.of the Internat.Topical Meeting on Advanced Reactors Safety, Pittsburgh, Pa., April 17-21, 1994 Vol. 2 S.1055-61

Arbeiten zur Anwendung des Codes CONTAIN auf Leichtwasserreaktoren. (1994)

Henneges, G., Schmuck, P., Scholtyssek, W.

Sicherheitsorientierte LWR-Forschung. Jahresbericht 1993.

Improvement of fission product transport modelling in the CONTAIN code (part II). (1994)

Scholtyssek, W.

Interner Bericht 32.22.07/03A (März 94)

Zur Eingrenzung des radiologischen Quellterms bei auslegungsueberschreitenden Ereignissen in zukuenftigen Druckwasserreaktoren. (1993)

Kessler, G., Kuczera, B., Ehrhardt, J., Henneges, G., Scholtyssek, W., Wiese, H.W.

KfK-5199 (August 93)

Investigations on ex-vessel core melt cooling in a future PWR containment. (1993)

Kuczera, B., Erbacher, F.J., Scholtyssek, W.

IAEA Technical Meeting on Thermohydraulic of Cooling Systems in Advanced Water-Cooled Reactors, Villigen, CH, May 25-27, 1993

An improved design concept for next generation PWR containments. (1992)

Eibl, J., Schlueter, F.H., Klatte, T., Breitung, W., Erbacher, F.J., Goeller, B., ...

Proc.of the 5th Workshop on Containment Integrity, Washington, D.C., May 12-14, 1992

Decay heat removal after a PWR core meltdown accident. (1992)

Scholtyssek, W., Alsmeyer, H., Erbacher, F.J.

Internat.Conf.on Design and Safety of Advanced Nuclear Power Plants, Tokyo, J, October 25-29, 1992 Proc. Vol.III S.23.2/1-2/9

Safety potential of a steel containment after a severe accident in a large fast breeder reactor. (1992)

Scholtyssek, W.

Internat.Conf.on Design and Safety of Advanced Nuclear Power Plants, Tokyo, J, October 25-29, 1992 Proc. Vol.IV S.41.1/1-1/8

Contain code applications for an improved containment concept of future light water reactors. (1992)

Henneges, G., Scholtyssek, W.

Sicherheitsorientierte LWR-Forschung. Jahresbericht 1991.

Sensitivitaetsstudie zur Langzeitentwicklung der Thermohydraulik in einem DWR Containment nach einem Kernschmelzestoerfall. (1992)

Scholtyssek, W.

Sicherheitsorientierte LWR-Forschung. Jahresbericht 1991.

Contain code applications for an improved containment concept of future light water reactors. (1991)

Henneges, G., Scholtyssek, W.

Proc.of the Internat.Topical Meeting on Safety of Thermal Reactors, Portland, Or., July 21-25, 1991

Validation of the contain code and application to accident consequence studies in a large fast breeder reactor. (1990)

Scholtyssek, W., Jacobs, G.

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

Liquid metal reactor applications of the contain code. (1990)

Carroll, D.E., Bergeron, K.D., Scholtyssek, W., Valdez, G.D., Gido, R.

Nuclear Technology, 91(1990) S.259-67

IRMA: interlaboratory comparison of fission and capture rate measurement techniques at MASURCA. (1988)

Scholtyssek, W., Angelone, M., D'Hondt, P., Granget, G., Marimbeau, P., Burbidge, B.H.L., ...

Proc.of the 1988 Internat. Reactor Physics Conf., Jackson Hole, Wyo., September 18-22, 1988 Vol. II S.II/271-II/282

Calculations of the RACINE 1I (IRMA experiment). Central reaction rate ratios and calculation/experiment comparisons. (1988)

Soule, R., Scholtyssek, W., Burbidge, B.H.L., Collins, P.J.

Proc.of the 1988 Internat. Reactor Physics Conf., Jackson Hole, Wyo., September 18-22, 1988 Vol. II S.II/283-II/296

Liquid metal reactor applications of the contain code. (1988)

Carroll, D.E., Bergeron, K.D., Gido, R., Scholtyssek, W., Valdez, G.D.

Internat.Meeting on the Safety of Next Generation Power Reactors, Seattle, Wash., May 1-5, 1988

Use of the Superphenix start-up experiments and of the critical experiment program RACINE for the validation of the physical characteristics of large size LMFBRs. (1986)

Salvatores, M., Recolin, J., Gourdon, J., Sztark, M., Martini, M., Scholtyssek, W., ...

Nuclear Energy of Today and Tomorrow ; 4th Internat. ENS/ANS Conf. and 9th Foratom Congress, Geneve, CH, June 1-6, 1986 ; Transactions

Parametric studies on heterogeneous cores for fast breeder reactors: the Pre-Racine and Racine experimental programs. (1984)

Humbert, G., Kappler, F., Martini, M., Norvez, G., Rimpault, G., Ruelle, B., ...

Nuclear Science and Engineering, 87(1984) S.233-51

Neutronenphysikalische Experimente an kritischen Anordnungen zur Unterstuetzung der nuklearen Auslegung und der Sicherheitsanalyse grosser Brueterkerne. (1983)

Helm, F., Boehme, R., Giese, H., Henneges, G., Kappler, F., Moellendorff, U.von, ...

KfK-Nachrichten, 15(1983) S.89-97

The RACINE programme. Physics and safety studies in heterogeneous configurations. (1982)

Scholtyssek, W., Humbert, G., Martini, M.

Jahrestagung Kerntechnik 82. Reaktortagung 1982. Mannheim, 4.-6.Mai 1982. Kerntechnische Ges.e.V. Deutsches Atomforum e.V.

Control-rod parametrical studies in the framework of the pre-racine and racine programs. (1982)

Humbert, G., Ruelle, B., Daguzan, G., Stanculescu, A., Kappler, F., Scholtyssek, W., ...

Proc.of the Topical Meeting on Advances in Reactor Physics and Core Thermal Hydraulics, Kiamesha Lake, N.Y., September 22-24, 1982 NUREG/CP-0034 (1982) Vol.1 S.148-61

An assessment of physical characteristics of heterogeneous configurations with variable fertile volume. (1982)

Scholtyssek, W., Daguzan, G., Humbert, G., Martini, M., Ruelle, B., Kappler, F., ...

Proc.of the Topical Meeting on Advances in Reactor Physics and Core Thermal Hydraulics, Kiamesha Lake, N.Y., September 22-24, 1982 NUREG/CP-0034 (1982) Vol.1 S.133-47

Main characteristics of the Racine programme developed by DEBENE, CNEN and CEA on Masurca for the heterogeneous core concept studies. (1979)

Bouget, Y.H., Conversano, R., Hammer, Ph., Helm, F., Martinelli, R., Scholtyssek, W.

Fast Reactor Physics, Internat.Symp., Aix-en-Provence, France, September 24-28, 1979

Comparative analyses of experiments in a large plutonium fuelled core. (1979)

Kappler, F., Giese, H., Helm, F., Scholtyssek, W., Pilate, S., Stevenson, J.M.

Fast Reactor Physics, Internat.Symp., Aix-en-Provence, France, September 24-28, 1979

Summary of results for the SNEAK-9 series of critical experiments and conclusions for the accuracy of predicted physics parameters of the SNR-300. (1978)

Helm, F., [Hrsg.], Boehme, R., Durance, G., Elbel-Raberain, A.M., Fehsenfeld, P., ...

KfK-2586 (August 78)

Physics investigations of sodium-cooled fast reactors: SNEAK assembly 9C. (1977)

Scholtyssek, W., [Hrsg.], Boehme, R., Fehsenfeld, P., Fischer, E.A., Giese, H., ...

KFK-2361 (April 77)

Use of ZPPR measurements as a support of criticality prediction for SNR-300. (1976)

Pilate, S., Wouters, R.De, Wehmann, U., Helm, F., Scholtyssek, W.

Joint Meeting of the American Nuclear Society, the Atomic Industrial Forum and the European Nuclear Society, Washington, D.C., November 15-19, 1976

Experimentelle Bestimmung der Brutrate in einem Plutonium-Core. (1975)

Jourdan, G., Boehme, R., Fehsenfeld, P., Scholtyssek, W.

Reaktortagung, Nuernberg, 8.-11. April 1975, Deutsches Atomforum e.V., Kerntechnische Ges.im Dt.Atomforum e.V. Leopoldshafen 1975: ZAED. S.237-40

Interlaboratory comparison of absolute fission rate and uranium-238 capture rate measurements in the MOL-#S#S secondary intermediate-energy standard neutron field. (1975)

Pinter, M., Scholtyssek, W., Fehsenfeld, P., Quaadvliet, W.H.J., Fabry, A., ...

4.Conference on Nuclear Cross Sections and Technology, Washington, March 3-7, 1975

Critical Experiments at SNEAK in Support of Fast Reactor Design. (1974)

Boehme, R., Helm, F., Pilate, S., Pinter, M., Scholtyssek, W.

Meeting on Advanced Reactors: Physics, Design and Economics, Atlanta, Ga., September 8-11, 1974

Analysis of the SNEAK Assemblies 9B and 9A-O. (1973)

Fehsenfeld, P., Jourdan, G., Pinter, M., Raberain, A.M., Scholtyssek, W.

19.Annual Meeting of the American Nuclear Society, Chicago/Ill., June 10-14, 1973

Studies of Unit k§0§0 Lattices in Metallic Uranium. Assemblies ZEBRA-8H, SNEAK-8, ERMINE and HARMONIE UK. (1973)

Fischer, E.A., Scholtyssek, W., Darrouzet, M., Chaudat, J.P., Ingram, G., Sanders, J.E.

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

Experimental Results from Two Pu-Fueled Fast Critical Assemblies. (1972)

Boehme, R., Fischer, E.A., Mc Grath, P.E., Scholtyssek, W.

National Topical Meeting on New Developments in Reactor Physics and Shielding, Kiamesha Lake, N.Y., September 12-15, 1972

Physikalische Untersuchungen an einfachen schnellen Pu-Cores. (1972)

Boehme, R., Fischer, E.A., Mc Grath, P., Scholtyssek, W.

Reaktortagung, Hamburg, 11. - 14. April 1972, Deutsches Atomforum e.V., Kerntechnische Ges. im Dt. Atomforum e.V., Leopoldshafen 1972: ZAED. S.98-101

Physikalische Untersuchungen an einem schnellen 'Null-Reaktivitaets-Core' mit angereichertem Uran. (1972)

Fischer, E.A., Bickel, W., Fehsenfeld, P., Pinter, M., Scholtyssek, W.

Reaktortagung, Hamburg, 11. - 14. April 1972, Deutsches Atomforum e.V., Kerntechnische Ges. im Dt. Atomforum e.V., Leopoldshafen 1972: ZAED. S.102-105

Zur Messung von Spalt- und Einfangraten mit Spaltspurdetektoren und Ge(Li)-Detektoren. (1971)

Korthaus, E., Guenther, G., Scholtyssek, W., Goel, B.

Reaktortagung, Bonn, 30.Maerz - 2. April 1971, Deutsches Atomforum e.V. Kerntechnische Ges. im Dt. Atomforum, Tagungsbericht. Leopoldshafen 1971: ZAED S.50-53