Győri Cs. VVER Ballooning Experiments. (1998) Megjelent: Enlarged Halden Programme Group Meeting, Compilation of presentations, HPR 349, Vol. II,
1268548
L Yegorova. Data Base on the Behavior of High Burnup Fuel Rods with Zr-1%Nb Cladding and U02 Fuel (VVER Type) under Reactivity Accident Conditions (NUREG/IA-0156). (1999)
Csordás AP. Investigation of aerosols released at high temperature from nuclear core models. (2000) JOURNAL OF NUCLEAR MATERIALS 0022-3115 282 2-3 205-215,
137364
Szakcikk (Folyóiratcikk) | Tudományos[137364]
Kissane M. On the nature of aerosols produced during a severe accident of a water-cooled nuclear reactor. (2008) NUCLEAR ENGINEERING AND DESIGN 0029-5493 238 10 2792-2800
Nagase F et al. Behavior of High Burn-up Fuel Cladding under LOCA Conditions. (2009) JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 0022-3131 1881-1248 46 7 763-769
Nagase F et al. Behavior of High Burn-up Fuel Cladding under LOCA Conditions. (2009) JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 0022-3131 1881-1248 46 7 763-769
Portier L. Influence of long service exposures on the thermal-mechanical behavior of Zy-4 and M5 (TM) alloys in LOCA conditions. (2005) AMERICAN SOCIETY FOR TESTING AND MATERIALS SPECIAL TECHNICAL PUBLICATION 1040-1695 1467 896-920
Van Dorsselaere et al. Views on R&D needs about in-vessel reflooding issues, with a focus on debris coolability. (2006) NUCLEAR ENGINEERING AND DESIGN 0029-5493 236 19-21 1976-1990
Windberg P. Integral Core Degradation Test with B4C Control Rod.. (2001) Megjelent: Proceedings of International Conference on Nuclear Energy In Central Europe 2001,
1236154
Adroguer B. Core loss during a severe accident (COLOSS). (2002) Megjelent: Proceedings of FISA-2001. EU Research in Reactor Safety pp. 247-260,
1236167
Bachellerie E et al. Generic approach for designing and implementing a passive autocatalytic recombiner PAR-system in nuclear power plant containments. (2003) NUCLEAR ENGINEERING AND DESIGN 0029-5493 221 1–3 151-165
De Bremaecke A. European Nuclear Thermodynamic Database Validated and Applicable in Seevere Acciden Codes ENTHALPY). (2002) Megjelent: Proceedings of FISA-2001. EU Research in Reactor Safety pp. 261-273,
137528
Hózer Z. CODEX-AIT-1 Experiment: Core Degradation Test under Air Ingress. (2002) KFKI 0368-5330 2002 02/G 1-83,
137482
Szakcikk (Folyóiratcikk) | Tudományos[137482]
T Hollands. Simulation of the Fuel Rod Bundle Tests QUENCH-10 and CODEX-AIT-1 Using the Program System ATHLET-CD 2.1A and Evalluation of the Air Ingress Model Basis. (2008)
Matus L. Oxidation and release of ruthenium in high temperature air. (2002),
1269270
Nem besorolt (Egyéb) | Tudományos[1269270]
Auvinen A et al. Progress on ruthenium release and transport under air ingress conditions. (2008) NUCLEAR ENGINEERING AND DESIGN 0029-5493 238 3418-3428
Végh J. Building Up an On-Line Plant Information System for the Emergency Response Centre of the Hungarian Nuclear Safety Directorate. (2002) NUCLEAR TECHNOLOGY 0029-5450 139 156-166,
137486
Szakcikk (Folyóiratcikk) | Tudományos[137486]
Eiler J. Overview of nuclear I&C activities in Hungary, 2005-2006. (2007) Megjelent: IAEA Technical Working Group on Nuclear Power Plant Control and Instrumentation (TWG on NPPCI) meeting, Vienna, Austria pp. 23-25
Egyéb konferenciaközlemény | Tudományos[24609903] [Admin láttamozott]
Adroguer B et al. Core loss during a severe accident (COLOSS). (2003) NUCLEAR ENGINEERING AND DESIGN 0029-5493 221 55-76,
137644
Szakcikk (Folyóiratcikk) | Tudományos[137644]
Mao J. et al. Structural integrity investigation for RPV with various cooling water levels under pressurized melting pool. (2018) MECHANICAL SCIENCES 2191-9151 9 1 147-160
Mao J. et al. Investigation on the RPV structural behaviors caused by various cooling water levels under severe accident. (2017) ENGINEERING FAILURE ANALYSIS 1350-6307 79 274-284
Mao JF et al. Investigation on Structural Behaviors of Reactor Pressure Vessel With the Effects of Critical Heat Flux and Internal Pressure. (2017) JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME 0094-9930 139 2
Zhu JW et al. Comparative Study on Reactor Pressure Vessel Failure Behaviors With Various Geometric Discontinuities Under Severe Accident. (2017) JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME 0094-9930 139 2
Mao JF et al. Study on structural failure of RPV with geometric discontinuity under severe accident. (2016) NUCLEAR ENGINEERING AND DESIGN 0029-5493 307 354-363
Mao JF et al. Investigation on multilayer failure mechanism of RPV with a high temperature gradient from core meltdown scenario. (2016) NUCLEAR ENGINEERING AND DESIGN 0029-5493 310 39-47
Mao JF et al. Creep deformation and damage behavior of reactor pressure vessel under core meltdown scenario. (2016) INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING 0308-0161 139 107-116
Miwa S. et al. Boron effects on fission product behavior under severe accident conditions. (2016) Megjelent: Top Fuel 2016: LWR Fuels with Enhanced Safety and Performance pp. 861-868
Mao JF et al. Creep and Damage Analysis of Reactor Pressure Vessel Considering Core Meltdown Scenario. (2015) Megjelent: PRESSURE VESSEL TECHNOLOGY: PREPARING FOR THE FUTURE pp. 1148-1161
Clément B. The Phebus fission product and source term international programmes. (2005) Megjelent: International Conference Nuclear Energy for New Europe 2005
Egyéb konferenciaközlemény | Tudományos[24617496] [Admin láttamozott]
Bachellerie E et al. Generic approach for designing and implementing a passive autocatalytic recombiner PAR-system in nuclear power plant containments. (2003) NUCLEAR ENGINEERING AND DESIGN 0029-5493 221 1–3 151-165
Fazekas Cs et al. Parameter estimation of a simple primary circuit model of a VVER plant. (2008) IEEE TRANSACTIONS ON NUCLEAR SCIENCE 0018-9499 55 5 Part 2 2643-2653
Hózer Z. CODEX and RUSET air oxidation experiments. (2003) Megjelent: Proceedings of the 5th PHEBUS FP Technical Seminar, IRSN, JRC-IE pp. 1-10,
1268597
Aszódi Attila et al. A 2003-as paksi üzemzavar műszaki okai és lefolyása. (2006) Megjelent: A 2003-as paksi üzemzavar műszaki okai és lefolyása pp. 11-63
Adroguer B et al. Core loss during a severe accident (COLOSS). (2005) NUCLEAR ENGINEERING AND DESIGN 0029-5493 235 173-198,
1236183
Sokszerzős vagy csoportos szerzőségű szakcikk (Folyóiratcikk) | Tudományos[1236183]
Tomashchik Dmitry Yu et al. Numerical assessment of PARAMETER-SF1 test on oxidation and melting of LWR fuel assembly under top flooding conditions. (2020) NUCLEAR ENGINEERING AND DESIGN 0029-5493 369
Hidaka A. B 4 C 制御材がシビアアクシデント時の炉心溶融過程およびヨウ素やセシウムの化学形に与える影響 [Effect of B4C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions]. (2015) TRANSACTION OF THE ATOMIC ENERGY SOCIETY OF JAPAN 1347-2879 2186-2931 14 1 51-61
Bottomley PDW et al. Severe accident research at the Transuranium Institute Karlsruhe: A review of past experience and its application to future challenges. (2014) ANNALS OF NUCLEAR ENERGY 0306-4549 1873-2100 65 345-356
ZHENG XY et al. Literature Review on Experiments and Models Associated with Degradation and Oxidation of Boron Carbide Control Material during Severe Accidents. (2014) Japan Atomic Energy Agency Review
Tanaka K et al. Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior. (2014) JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 0022-3131 1881-1248 51 7-8 876-885
de Luze O. Degradation and oxidation of B4C control rod segments at high temperatures. A review and code interpretation of the BECARRE program. (2013) NUCLEAR ENGINEERING AND DESIGN 0029-5493 259 150-165
Bottomley PDW. Severe accident research at ITU, Karlsruhe: A review of past experience and its application to future challenges.. (2012) International Meeting on Severe Accident Assessment and Management 2012: Lessons Learned from Fukushima Dai-ichi San Diego 146-157
Mueller K et al. Validation of severe accident codes on the phebus fission product tests in the framework of the PHEBEN-2 project. (2008) NUCLEAR TECHNOLOGY 0029-5450 163 2 209-227
Mueller K et al. Validation of severe accident codes on the phebus fission product tests in the framework of the PHEBEN-2 project. (2008) NUCLEAR TECHNOLOGY 0029-5450 163 2 209-227
Dominguez C et al. Investigation on boron carbide oxidation for nuclear reactor safety: Experiments in highly oxidising conditions. (2008) JOURNAL OF NUCLEAR MATERIALS 0022-3115 374 3 473-481
Hózer Z et al. Ballooning experiments with VVER cladding. (2005) NUCLEAR TECHNOLOGY 0029-5450 152 3 273-285,
137814
Szakcikk (Folyóiratcikk) | Tudományos[137814]
Goldberg Ezequiel et al. New module for simulating experiments without irradiation included in the DIONISIO 3.0 code. (2021) NUCLEAR ENGINEERING AND DESIGN 0029-5493 374
Williamson Richard L. et al. BISON: A Flexible Code for Advanced Simulation of the Performance of Multiple Nuclear Fuel Forms. (2021) NUCLEAR TECHNOLOGY 0029-5450 207 7 954-980
Hosseini Seyed Ali et al. Re-assessment of accumulators performance to identify VVER-1000 vulnerabilities against various break sizes of SB-LOCA along with SBO. (2020) PROGRESS IN NUCLEAR ENERGY 0149-1970 119
Nagy R et al. Optical observation of the ballooning and burst of E110 and E110G cladding tubes. (2018) NUCLEAR ENGINEERING AND DESIGN 0029-5493 339 194-201
Nagy R. et al. Optical measurement of the high temperature ballooning of nuclear fuel claddings. (2018) REVIEW OF SCIENTIFIC INSTRUMENTS 0034-6748 1089-7623 89 12
Brachet JC et al. Study of secondary hydriding at high temperature in zirconium based nuclear fuel cladding tubes by coupling information from neutron radiography/tomography, electron probe micro analysis, micro elastic recoil detection analysis and laser induced breakdown spectroscopy microprobe. (2017) JOURNAL OF NUCLEAR MATERIALS 0022-3115 488 267-286
Grosse M et al. Neutron Imaging Investigations of the Secondary Hydriding of Nuclear Fuel Cladding Alloys during Loss of Coolant Accidents. (2015) Megjelent: PROCEEDINGS OF THE 10TH WORLD CONFERENCE ON NEUTRON RADIOGRAPHY (WCNR-10) pp. 436-444
Grosse M. Analysis of the secondary cladding hydrogenation during the quench-LOCA bundle tests with zircaloy-4 claddings and its influence on the cladding embrittlement. (2015) Megjelent: 17th International Symposium on Zirconium in the Nuclear Industry pp. 1054-1073
Grosse M et al. Parameters influencing the hydrogen concentration and distribution in cladding tubes after LOCA: Results of bundle-scale experiments and modeling. (2014) Megjelent: International Congress on Advances in Nuclear Power Plants, ICAPP 2014 pp. 850-856
Grosse MK et al. Neutron radiography and tomography investigations of the secondary hydriding of zircaloy-4 during simulated loss of coolant nuclear accidents. (2013) Megjelent: 7th International Topical Meeting on Neutron Radiography, ITMNR 2012 pp. 294-306
Grosse M et al. Neutron imaging investigations of the hydrogen related degradation of the mechanical properties of zircaloy-4 cladding tubes. (2013) Megjelent: 2012 MRS Fall Meeting pp. 89-94
Hózer Z. Release of Radioactive Isotopes from Dammaged Fuel. (2005) Megjelent: Primary and Secondary Side Water Chemistry of Nuclear Power Plants. Proceedings of the 6th International Seminar Budapest 2005,
1236188
Magallon D et al. European expert network for the reduction of uncertainties in severe accident safety issues (EURSAFE). (2005) NUCLEAR ENGINEERING AND DESIGN 0029-5493 235 2-4 309-346,
1236185
Szakcikk (Folyóiratcikk) | Tudományos[1236185]
Xing Ji et al. Scaling analysis and evaluation for the design of integral test facility of HPR1000 containment (PANGU). (2021) NUCLEAR ENGINEERING AND DESIGN 0029-5493 373
Blaesius Christoph et al. Methods for failure assessment of NPP pressure boundary under severe accident loading. (2021) NUCLEAR ENGINEERING AND DESIGN 0029-5493 374
Bachrata Andrea et al. A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors. (2021) JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2332-8983 2332-8975 7 3
Miyahara Naoya et al. Experimental study on transport behavior of cesium iodide in the reactor coolant system under LWR severe accident conditions. (2020) JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 0022-3131 1881-1248
Pshenichnikov Anton et al. New research programme of JAEA/CLADS to reduce the knowledge gaps revealed after an accident at Fukushima-1: introduction of boiling water reactor mock-up assembly degradation test programme. (2019) JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 0022-3131 1881-1248
Miyahara Naoya et al. Chemical reaction kinetics dataset of Cs-I-B-Mo-O-H system for evaluation of fission product chemistry under LWR severe accident conditions. (2019) JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 0022-3131 1881-1248 56 2 228-240
Gouello Melany et al. Contribution to the understanding of iodine transport under primary circuit conditions: Csi/Cd and Csi/Ag interactions in condensed phase. (2018) NUCLEAR MATERIALS AND ENERGY 2352-1791 17 259-268
Kim Han-Chul et al. Development of a Korean roadmap for technical issue resolution for fission product behavior during severe accidents. (2017) NUCLEAR ENGINEERING AND TECHNOLOGY 1738-5733 49 8 1575-1588
Miwa S et al. Prediction of the effects of boron release kinetics on the vapor species of cesium and iodine fission products. (2016) PROGRESS IN NUCLEAR ENERGY 0149-1970 92 254-259
Tyrpekl V et al. Prototypic corium oxidation and hydrogen release during the Fuel-Coolant Interaction. (2015) ANNALS OF NUCLEAR ENERGY 0306-4549 1873-2100 75 210-218
Suehiro S et al. Development of the source term PIRT based on findings during Fukushima Daiichi NPPs accident. (2015) NUCLEAR ENGINEERING AND DESIGN 0029-5493 286 0 163-174
Hidaka A. B 4 C 制御材がシビアアクシデント時の炉心溶融過程およびヨウ素やセシウムの化学形に与える影響 [Effect of B4C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions]. (2015) TRANSACTION OF THE ATOMIC ENERGY SOCIETY OF JAPAN 1347-2879 2186-2931 14 1 51-61
Sakai N et al. Validation of MAAP model enhancement for Fukushima Dai-ichi accident analysis with Phenomena Identification and Ranking Table (PIRT). (2014) JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 0022-3131 1881-1248 51 7-8 951-963
Bottomley PDW et al. Severe accident research at the Transuranium Institute Karlsruhe: A review of past experience and its application to future challenges. (2014) ANNALS OF NUCLEAR ENERGY 0306-4549 1873-2100 65 345-356
Sakai N. PHENOMENA IDENTIFICATION RANKING TABLE (PIRT) FOR THE MAAP ENHANCEMENT PROJECT. (2014) Megjelent: PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 6
Tyrpekl V et al. Material effect in the nuclear fuel-coolant interaction: Analyses of prototypic melt fragmentation and solidification in the KROTOS facility. (2014) NUCLEAR TECHNOLOGY 0029-5450 186 2 229-240
Hoseyni SM et al. A systematic framework for effective uncertainty assessment of severe accident calculations; Hybrid qualitative and quantitative methodology. (2014) RELIABILITY ENGINEERING & SYSTEM SAFETY 0951-8320 125 22-35
Sakai N. Phenomena identification ranking table (PIRT) for the MAAP enhancement project. (2013) Megjelent: 2013 21st International Conference on Nuclear Engineering, ICONE 2013
Sugimoto J. Important severe accident research issues after accident at Fukushima Daiichi nuclear power station. (2013) Megjelent: 2013 21st International Conference on Nuclear Engineering, ICONE 2013
Paci S et al. Spreading of Excellence in SARNET Network on Severe Accidents: The Education and Training Programme. (2012) SCIENCE AND TECHNOLOGY OF NUCLEAR INSTALLATIONS 1687-6075 1687-6083 2012
