Works matching DE "NUCLEAR fuel claddings"

Results: 296

The use of measurements of the velocity of ultrasound to determine the stress-strain state of metal articles.

Published in:

Measurement Techniques, 2010, v. 53, n. 4, p. 439, doi. 10.1007/s11018-010-9522-x

By:

Zuev, L.;
Semukhin, B.;
Lunev, A.

Publication type:

Article

Analysis of Thermophysical Justification of the Applicability of Accident Tolerant Fuel for Nuclear Power Plants: Current Concepts, Technologies, and Chemical Stability of Accident Tolerant Fuel.

Published in:

High Temperature, 2024, v. 62, n. 5, p. 669, doi. 10.1134/S0018151X25700191

By:

Zabirov, A. R.;
Molotova, I. A.;
Yagov, V. V.;
Sidelev, D. V.;
Yashnikov, D. A.;
Shevchenko, S. A.

Publication type:

Article

Distinctive Oxide Films Develop on the Surface of FeCrAl as the Environment Changes for Nuclear Fuel Cladding.

Published in:

Corrosion & Materials Degradation, 2024, v. 5, n. 1, p. 109, doi. 10.3390/cmd5010006

By:

Qu, Haozheng;
Yin, Liang;
Larsen, Michael;
Rebak, Raul B.

Publication type:

Article

EXPERIMENTAL INVESTIGATION OF CRITICAL HEAT FLUX IN ANNULUS AT LOW PRESSURE AND LOW FLOW PARAMETERS.

Published in:

Acta Polytechnica CTU Proceedings, 2020, v. 28, p. 50, doi. 10.14311/APP.2020.28.0050

By:

VLČEK, DANIEL;
SUK, LADISLAV;
ŠTEVANKA, KAMIL;
PETROSYAN, TARON

Publication type:

Article

INVESTIGATION OF CRITICAL HEAT FLUX ON ABRADED INCONEL 625 TUBE.

Published in:

Acta Polytechnica CTU Proceedings, 2020, v. 28, p. 15, doi. 10.14311/APP.2020.28.0015

By:

SUK, LADISLAV;
ŠTEVANKA, KAMIL;
PETROSYAN, TARON;
VLČEK, DANIEL

Publication type:

Article

HIGH-TEMPERATURE OXIDATION OF CHROME-NICKEL ALLOY.

Published in:

Acta Polytechnica CTU Proceedings, 2020, v. 28, p. 8, doi. 10.14311/APP.2020.28.0008

By:

CHALUPOVÁ, ADÉLA;
STEINBRÜCK, MARTIN;
GROSSE, MIRCO;
KREJČÍ, JAKUB;
ŠEVEČEK, MARTIN

Publication type:

Article

EXPERIMENTAL STUDY OF DAMAGED CR-COATED FUEL CLADDING IN POST-ACCIDENT CONDITIONS.

Published in:

Acta Polytechnica CTU Proceedings, 2020, v. 28, p. 1, doi. 10.14311/APP.2020.28.0001

By:

ČERVENKA, PETR;
KREJČÍ, JAKUB;
CVRČEK, LADISLAV;
ROZKOŠNÝ, VOJTĚCH;
MANOCH, FRANTIŠEK;
RADA, DAVID;
KABÁTOVÁ, JITKA

Publication type:

Article

NANOINDENTATION OF HYDROGEN ENRICHED Zr-1Nb ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS.

Published in:

Acta Polytechnica CTU Proceedings, 2020, v. 27, p. 155, doi. 10.14311/APP.2020.27.0155

By:

LIBERA, ONDŘEJ;
HALODOVÁ, PATRICIE;
GÁVELOVÁ, PETRA;
KREJČÍ, JAKUB

Publication type:

Article

Multi‐objective optimization design of U3Si2–FeCrAl accident tolerant fuel elements based on Gaussian process and genetic algorithm.

Published in:

International Journal of Energy Research, 2022, v. 46, n. 9, p. 12108, doi. 10.1002/er.7976

By:

Chen, Hao;
Zhou, Yi;
Li, Quan;
Liu, Zhenhai;
Qi, Feipeng;
Ma, Chao;
Zhao, Bo;
Huang, Yongzhong

Publication type:

Article

Conceptual design of a long cycle small modular reactor core with annular UO2 and FCM (TRU) fuels.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 11957, doi. 10.1002/er.5957

By:

Choi, Jae Yeon;
Hong, Ser Gi;
Kwon, Hyuk

Publication type:

Article

Computational model‐based design of molten salt electrorefining process for high‐purity zirconium metal recovery from spent nuclear fuel.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 11775, doi. 10.1002/er.5724

By:

Sohn, Sungjune;
Choi, Sungyeol;
Park, Jaeyeong;
Hwang, Il Soon

Publication type:

Article

Impacts of an ATF cladding on neutronic performances of the soluble‐boron‐free ATOM core.

Published in:

International Journal of Energy Research, 2020, v. 44, n. 10, p. 8193, doi. 10.1002/er.5322

By:

Nguyen, Xuan Ha;
Jang, Seongdong;
Kim, Yonghee

Publication type:

Article

Investigation of core meltdown phenomena and radioactive materials release in VVER‐1000/V446 nuclear reactor at severe accident condition due to LBLOCA along SBO.

Published in:

International Journal of Energy Research, 2020, v. 44, n. 10, p. 8113, doi. 10.1002/er.5056

By:

Ghasemi, A.;
Pirouzmand, A.;
Kamyab, S.

Publication type:

Article

Untargeted Metabolomics Reveals a Complex Impact on Different Metabolic Pathways in Scallop Mimachlamys varia (Linnaeus, 1758) after Short-Term Exposure to Copper at Environmental Dose.

Published in:

Metabolites (2218-1989), 2021, v. 11, n. 12, p. 862, doi. 10.3390/metabo11120862

By:

Hamani, Vincent;
Ory, Pascaline;
Bodet, Pierre-Edouard;
Murillo, Laurence;
Graber, Marianne

Publication type:

Article

Film study of pellet-clad interactions using cerium oxide as a surrogate.

Published in:

New Mexico Journal of Science, 2016, v. 50, n. 1, p. 83

By:

PERALAS, DIANA;
HATTAR, KHALID;
BOYLE, TIMOTHY;
DINGERVILLE, REMI

Publication type:

Article

True stress measurement of nuclear fuel rod cladding material subjected to DSA regime.

Published in:

Neural Computing & Applications, 2017, v. 28, p. 119, doi. 10.1007/s00521-016-2298-4

By:

Garg, A.;
Panda, Biranchi;
Tai, K.

Publication type:

Article

Out-of-plane capacity of cladding panel-to-structure connections in one-story R/C precast structures.

Published in:

Bulletin of Earthquake Engineering, 2020, v. 18, n. 15, p. 6849, doi. 10.1007/s10518-020-00962-5

By:

Menichini, Giovanni;
Del Monte, Emanuele;
Orlando, Maurizio;
Vignoli, Andrea

Publication type:

Article

Effect of Nb and La on Precipitates, Yield Strength and Toughness of FeCrAl Alloy.

Published in:

Steel Research International, 2024, v. 95, n. 12, p. 1, doi. 10.1002/srin.202400553

By:

Zhang, Huai;
Shi, Chengbin;
Luo, Yiwa

Publication type:

Article

INHERENT SAFETY OF FUELS FOR ACCELERATOR-DRIVEN SYSTEMS.

Published in:

Nuclear Technology, 2005, v. 151, n. 3, p. 314, doi. 10.13182/NT05-A3654

By:

Eriksson, M.;
Wallenius, J.;
Jolkkonen, M.;
Cahalan, J. E.

Publication type:

Article

APPLICATION OF THE POST-BOILING-TRANSITION STANDARD TO LICENSING ANALYSIS.

Published in:

Nuclear Technology, 2005, v. 152, n. 1, p. 105, doi. 10.13182/NT05-A3663

By:

Mizokami, Shinya;
Kitamura, Hideya;
Kudo, Yoshiro;
Komura, Seiichi;
Nagata, Yoshifumi;
Morooka, Shinichi

Publication type:

Article

Characterisation of AlCrCuFeMox high entropy alloys for nuclear fuel cladding.

Published in:

Materials Science & Technology, 2022, v. 38, n. 18, p. 1563, doi. 10.1080/02670836.2022.2093000

By:

Zhu, Xincheng;
Tao, Zhenrui;
Wang, Chunji;
Zhang, Yanwei;
Bai, Guanghai;
Lan, Rui

Publication type:

Article

Analysis of the technological process of welding a membrane wall with Inconel 625 nickel alloy.

Published in:

International Journal of Advanced Manufacturing Technology, 2023, v. 127, n. 5/6, p. 3031, doi. 10.1007/s00170-023-11499-7

By:

Majerik, Jozef;
Slany, Martin;
Chochlikova, Henrieta;
Sedlak, Josef;
Zouhar, Jan;
Zemcik, Oskar;
Barenyi, Igor;
Kolomy, Stepan;
Escherova, Jana

Publication type:

Article

A precision grinding technology for zirconium alloy tubes based on ultrasonic wall thickness automatic measurement system.

Published in:

International Journal of Advanced Manufacturing Technology, 2022, v. 121, n. 1/2, p. 323, doi. 10.1007/s00170-022-09314-w

By:

Zou, Lai;
Li, Heng;
Wang, Wenxi;
Huang, Yun;
Li, Yutong

Publication type:

Article

Energy consumption modeling of additive-subtractive hybrid manufacturing based on cladding head moving state and deposition efficiency.

Published in:

International Journal of Advanced Manufacturing Technology, 2022, v. 120, n. 11/12, p. 7755, doi. 10.1007/s00170-022-09265-2

By:

Liu, Wen;
Wei, Haiying;
Zhang, Min;
Luo, Yaoen;
Zhang, Yi

Publication type:

Article

Crack nucleation in rod-type nuclear fuel pellet.

Published in:

Mathematics & Mechanics of Solids, 2019, v. 24, n. 3, p. 668, doi. 10.1177/1081286517753977

By:

Mirsalimov, Vagif

Publication type:

Article

An impedance-based diameter gauge for in-pile fuel deformation measurements.

Published in:

Instrumentation Science & Technology, 2019, v. 47, n. 6, p. 611, doi. 10.1080/10739149.2019.1616207

By:

Fleming, Austin;
Al Rashdan, Ahmad;
Jensen, Colby;
Calderoni, Pattrick

Publication type:

Article

CORROSION RESISTANCE OF TRADITIONAL AND ADVANCED FUEL ROD CLADDING MATERIALS FOR WATER-COOLED REACTORS.

Published in:

Progress in Physics of Metals / Uspehi Fiziki Metallov, 2024, v. 25, n. 2, p. 243, doi. 10.15407/ufm.25.02.243

By:

ZUYOK, V. A.;
KOVALENKO, Yu. V.;
SHTEFAN, V. V.;
RUD, R. O.;
TRETIAKOV, M. V.;
KUSHTYM, Ya. O.

Publication type:

Article

Nondestructive Elemental Diagnostics of the Fuel-Rod Cladding Surface by the Ion-Beam and X-Ray Analytical Methods.

Published in:

Instruments & Experimental Techniques, 2021, v. 64, n. 1, p. 63, doi. 10.1134/S0020441221010085

By:

Egorov, V. K.;
Egorov, E. V.;
Kalin, B. A.;
Safonov, D. A.

Publication type:

Article

Effect of Zr Impregnation on Clay-Based Materials for H 2 O 2 -Assisted Photocatalytic Wet Oxidation of Winery Wastewater.

Published in:

Water (20734441), 2020, v. 12, n. 12, p. 3387, doi. 10.3390/w12123387

By:

Guimarães, Vanessa;
Teixeira, Ana R.;
Lucas, Marco S.;
Peres, José A.

Publication type:

Article

Best estimate analysis of processes in RBMK fuel rods during the operation cycle.

Published in:

Mechanika, 2011, v. 17, n. 4, p. 387, doi. 10.5755/j01.mech.17.4.567

By:

Kaliatka, T.;
Marao, A.;
Karalevičius, R.;
Ušpuras, E.;
Kaliatka, A.

Publication type:

Article

Investigation of resistance of nuclear fuel cladding to hydride cracking.

Published in:: Mechanika, 2010, v. 85, n. 5, p. 25
Publication type:: Article

Fabrication and characterisation of ZrSi2 ceramics via reactive hot-pressing.

Published in:

Advances in Applied Ceramics: Structural, Functional & Bioceramics, 2022, v. 121, n. 5-8, p. 166, doi. 10.1080/17436753.2022.2139448

By:

Jayakody Mudiyanselage, Yasith Chameendra;
Ramachandran, Karthikeyan;
Daniel Jayaseelan, Doni

Publication type:

Article

Granular structure of chromium coatings prepared by arc ion plating for accident-tolerant fuel cladding.

Published in:

Journal Of Sichuan University (Natural Sciences Division) / Sichuan Daxue Xuebao-Ziran Kexueban, 2022, v. 59, n. 3, p. 035002-1, doi. 10.19907/j.0490-6756.2022.03500

By:

LIU Shao-Qiang;
GONG Wen-Juan;
MA Zhao-Dan-Dan;
CHEN Huan;
WANG Jing;
ZHANG Rui-Qian;
ZOU Yu;
YANG Ji-Jun;
ZHAN Chang-Yong

Publication type:

Article

Neutronic Analysis of Accident-Tolerant Cladding Materials in 3D Full Core BEAVRS PWR Benchmark Using OpenMC Code.

Published in:

International Journal of Energy Research, 2024, v. 2024, p. 1, doi. 10.1155/2024/8811265

By:

Alamri, Khalid A.;
Alqahtani, Meshari M.;
Alomari, Abdullah S.;
Almarshad, Abdullah I.

Publication type:

Article

QUALIFICATION OF NUCLEAR REACTOR NOMINAL POWER UPGRADES.

Published in:

Proceedings of Odessa Polytechnic University / Odes'kyi Politechnichnyi Universytet Pratsi, 2024, v. 70, n. 2, p. 88, doi. 10.15276/opu.2.70.2024.11

By:

Skalozubov, V.;
Katsarskyi, Iu.;
Komarov, Iu.;
Mazur, Ye.;
Kochnieva, V.

Publication type:

Article

MODERNIZED LOSS-OF-COOLANT & BLACKOUT ACCIDENT MANAGEMENT STRATEGY AT NUCLEAR POWER PLANTS WITH WWER.

Published in:

Proceedings of Odessa Polytechnic University / Odes'kyi Politechnichnyi Universytet Pratsi, 2020, v. 60, n. 1, p. 53, doi. 10.15276/opu.1.60.2020.06

By:

Skalozubov, V.;
Spinov, V.;
Spinov, D.;
Gablaya, T.;
Kochnyeva, V.;
Komarov, Yu.

Publication type:

Article

SUBSTANTIATION OF MODERNIZED BLACKOUT & LOSS-OF-COOLANT ACCIDENT MANAGEMENT STRATEGY AT NUCLEAR POWER PLANTS WITH WWER.

Published in:

Proceedings of Odessa Polytechnic University / Odes'kyi Politechnichnyi Universytet Pratsi, 2020, v. 61, n. 2, p. 70, doi. 10.15276/opu.2.61.2020.08

By:

Skalozubov, V.;
Spinov, V.;
Spinov, D.;
Gablaya, T.;
Kochnyeva, V.;
Komarov, Yu.

Publication type:

Article

MODEL FOR CALCULATING THE TEMPERATURE IN THE FUEL RODS OF THE FA-X FUEL ASSEMBLY PRODUCED FOR SUBCRITICAL INSTILLATION AND REACTOR WWR-M.

Published in:

Proceedings of Odessa Polytechnic University / Odes'kyi Politechnichnyi Universytet Pratsi, 2020, v. 61, n. 2, p. 31, doi. 10.15276/opu.2.61.2020.04

By:

Chernov, I.;
Kushtym, А.

Publication type:

Article

SUBSTANTIATION OF STRATEGIES FOR THE MANAGEMENT OF BLACKOUT ACCIDENT AT NUCLEAR POWER PLANTS WITH WWER-TYPE REACTORS.

Published in:

Proceedings of Odessa Polytechnic University / Odes'kyi Politechnichnyi Universytet Pratsi, 2019, v. 59, n. 3, p. 44, doi. 10.15276/opu.3.59.2019.06

By:

Skalozubov, V.;
Spinov, V.;
Spinov, D.;
Gablaya, T.;
Kochnyeva, V.;
Komarov1, Yu.

Publication type:

Article

QUALIFICATION OF AFTERHEAT REMOVAL PASSIVE SYSTEM FROM REACTOR TO MANAGE BLACKOUT ACCIDENTS.

Published in:

Proceedings of Odessa Polytechnic University / Odes'kyi Politechnichnyi Universytet Pratsi, 2019, v. 59, n. 3, p. 19, doi. 10.15276/opu.3.59.2019.03

By:

Skalozubov, V.;
Spinov, V.;
Spinov, D.;
Gablaya, T.;
Kochnyeva, V.;
Skalozubov, K.

Publication type:

Article

INCREASING LONG-TERM STRENGTH OF Zr-1%Nb ALLOY BY DIFFUSIVE HARDENING OF NEAR-SURFACE LAYER.

Published in:

Proceedings of Odessa Polytechnic University / Odes'kyi Politechnichnyi Universytet Pratsi, 2018, v. 55, n. 2, p. 59, doi. 10.15276/opu.2.55.2018.06

By:

Voyevodin, V.;
Trush, V.;
Fedirko, V.;
Luk’yanenko, A.;
Stoev, P.;
Tіkhonovsky, M.

Publication type:

Article

AUTOMATED SYSTEM FOR CONTROL OF VVER-1000 FUEL PROPERTIES CONSIDERING FUEL CLADDING DAMAGE PARAMETER.

Published in:

Proceedings of Odessa Polytechnic University / Odes'kyi Politechnichnyi Universytet Pratsi, 2018, v. 54, n. 1, p. 46, doi. 10.15276/opu.1.54.2018.06

By:

Pelykh, S.;
Frolov, М.;
Nalyvayko, А.;
Huiyu Zhou

Publication type:

Article

THE PROBLEM OF MINIMIZING THE RADIOACTIVE LEAKAGE INTO THE VVER CIRCUIT UNDER NORMAL CONDITIONS.

Published in:

Proceedings of Odessa Polytechnic University / Odes'kyi Politechnichnyi Universytet Pratsi, 2017, v. 51, n. 2, p. 39, doi. 10.15276/opu.2.52.2017.06

By:

Pelykh, S. N.;
Frolov, М. А.;
Nalyvayko, А. V.;
Zhou, Huiyu

Publication type:

Article

Study on frictional behavior of SiCf/SiC composite clad tube clamping condition under nuclear irradiation.

Published in:

Friction (2223-7704), 2024, v. 12, n. 5, p. 919, doi. 10.1007/s40544-023-0805-z

By:

Xiao, Chenglong;
Shen, Liangliang;
Zhu, Tianqi;
Tang, Jianbo;
Xie, Ximing;
Fan, Xinyu;
Xu, Jian;
Ren, Zhiying

Publication type:

Article

An efficient instance segmentation approach for studying fission gas bubbles in irradiated metallic nuclear fuel.

Published in:

Scientific Reports, 2023, v. 13, n. 1, p. 1, doi. 10.1038/s41598-023-47914-y

By:

Sun, Shoukun;
Xu, Fei;
Cai, Lu;
Salvato, Daniele;
Dilemma, Fidelma;
Capriotti, Luca;
Xian, Min;
Yao, Tiankai

Publication type:

Article

ANALYSIS OF NUCLEAR SAFETY IN DIVERSIFICATION OF WESTINGHOUSE FUEL ASSEMBLIES AT WWER-1000.

Published in:

Nuclear Physics & Atomic Energy, 2019, v. 20, n. 2, p. 159, doi. 10.15407/jnpae2019.02.159

By:

Skalozubov, V. I.;
Kozlov, I. L.;
Komarov, Yu. A.;
Chulkin, O. A.;
Piontkovkyi, O. I.

Publication type:

Article

Effect of Heating Rate on Hydride Reorientation Behavior of Zirconium Alloy Tubes under Non-Stress Loading.

Published in:

Metals (2075-4701), 2024, v. 14, n. 10, p. 1126, doi. 10.3390/met14101126

By:

Hui, Boning;
Chen, Mingju;
Li, Xinyi;
Chen, Biao;
Li, Yuli;
Zhou, Jun;
Tang, Rongtao;
Li, Jinshan

Publication type:

Article

Cladding Failure Modelling for Lead-Based Fast Reactors: A Review and Prospects.

Published in:

Metals (2075-4701), 2023, v. 13, n. 9, p. 1524, doi. 10.3390/met13091524

By:

Wang, Guan;
Wang, Zhaohao;
Yun, Di

Publication type:

Article

Optimization of the Pressure Resistance Welding Process for Nuclear Fuel Cladding Coupling Experimental and Numerical Approaches.

Published in:

Metals (2075-4701), 2023, v. 13, n. 2, p. 291, doi. 10.3390/met13020291

By:

Mabrouki, Mohamed;
Gonçalves, Diogo;
Pascal, Serge;
Bertheau, Denis;
Henaff, Gilbert;
Poulon-Quintin, Angéline

Publication type:

Article

Simplified Model of a High Burnup Spent Nuclear Fuel Rod under Lateral Impact Considering a Stress-Based Failure Criterion.

Published in:

Metals (2075-4701), 2021, v. 11, n. 10, p. 1631, doi. 10.3390/met11101631

By:

Kim, Seyeon;
Lee, Sanghoon

Publication type:

Article