Works matching DE "NUCLEAR fuel elements"

Results: 280

AI-Powered Convolutional Neural Network Surrogate Modeling for High-Speed Finite Element Analysis in the NPPs Fuel Performance Framework.

Published in:

Energies (19961073), 2025, v. 18, n. 10, p. 2557, doi. 10.3390/en18102557

By:

Cancemi, Salvatore A.;
Ambrutis, Andrius;
Povilaitis, Mantas;
Lo Frano, Rosa

Publication type:

Article

Describing oxygen self-diffusion in PuO by connecting point defect parameters with bulk properties.

Published in:

Journal of Materials Science: Materials in Electronics, 2015, v. 26, n. 5, p. 3287, doi. 10.1007/s10854-015-2829-2

By:

Chroneos, A.;
Fitzpatrick, M.;
Tsoukalas, L.

Publication type:

Article

Studying Zirconium Surface Oxidation by Active Thermal Method.

Published in:

Russian Journal of Nondestructive Testing, 2021, v. 57, n. 12, p. 1120, doi. 10.1134/S1061830921120032

By:

Chernykh, S. E.;
Kostin, V. N.;
Komolikov, Yu. I.

Publication type:

Article

A method for analytical monitoring of surface deposits on jackets of fuel elements of reactors with water heat carrier.

Published in:

Inorganic Materials, 2010, v. 46, n. 15, p. 1640, doi. 10.1134/S0020168510150082

By:

Smirnova, I.

Publication type:

Article

New high-performance light water reactor core concept with mixed cycle length operation.

Published in:

International Journal of Energy Research, 2018, v. 42, n. 1, p. 53, doi. 10.1002/er.3738

By:

Jeong, Eun;
Choe, Jiwon;
Zhang, Peng;
Shin, Ho Cheol;
Lee, Deokjung

Publication type:

Article

Reactivity and kinetic parameter evolutions for the core height and boron concentration of the fixed bed nuclear reactor.

Published in:

International Journal of Energy Research, 2018, v. 42, n. 1, p. 178, doi. 10.1002/er.3515

By:

Van Thong, Ha;
Minh, Do Thi Nguyet;
Şahin, Sümer;
Hoang, Truong Huy;
Sefidvash, Farhang

Publication type:

Article

Plutonium, Nuclear Power, and Nuclear Weapons.

Published in:

Issues in Science & Technology, 1999, v. 15, n. 3, p. 29

By:

Wagner Jr., Ricahrd L.;
Aarhur, Edward D.;
Cunningham, Paul T.

Publication type:

Article

Development, characterization and dissolution behavior of calciumaluminoborate glass wasteforms to immobilize rare-earth oxides.

Published in:

Scientific Reports, 2018, p. 1, doi. 10.1038/s41598-018-23665-z

By:

Kim, Miae;
Corkhill, Claire L.;
Hyatt, Neil C.;
Jong Heo

Publication type:

Article

PRELIMINARY STUDY FOR DESIGN CORE OF NUCLEAR RESEARCH REACTOR OF TRIGA BANDUNG USING FUEL ELEMENT PLATE MTR.

Published in:

Annals of the Faculty of Engineering Hunedoara - International Journal of Engineering, 2016, v. 14, n. 4, p. 107

By:

RAMADHAN, Anwar Ilmar;
SUWONO, Aryadi;
UMAR, Efrizon;
TANDIAN, Nathanael Panagung

Publication type:

Article

Behavior of Zr--1Nb alloy in coarse- and ultrafine-grain states under laser-induced shock wave loading.

Published in:

Fracture & Structural Integrity, 2023, n. 66, p. 164, doi. 10.3221/IGF-ESIS.66.10

By:

Ledon, Dmitry;
Balakhnin, Aleksandr;
Uvarov, Sergey;
Bannikova, Irina;
Bayandin, Yuriy;
Naimark, Oleg

Publication type:

Article

Seismic stability of two interconnected steel structures freely standing on the floor.

Published in:

Bulletin of Earthquake Engineering, 2016, v. 14, n. 11, p. 3259, doi. 10.1007/s10518-016-9936-1

By:

Saraswat, A.;
Reddy, G.;
Umashankar, C.;
Parulekar, Y.;
Ghosh, A.

Publication type:

Article

BEHAVIOR OF VVER FUEL RODS TESTED UNDER SEVERE ACCIDENT CONDITIONS IN THE CODEX FACILITY.

Published in:

Nuclear Technology, 2006, v. 154, n. 3, p. 302

By:

Hózer, Zoltán;
Maróti, László;
Windberg, Péter;
Matus, Lajos;
Nagy, Imre;
Gyenes, György;
Horváth, Márta;
Pintér, Anna;
Balaskó, Márton;
Czitrovszky, Aladár;
Jani, Peter;
Nagy, Attila;
Prokopiev, Oleg;
Tóth, Béla

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

ANALYSIS OF ACCIDENTS AT THE PAKISTAN RESEARCH REACTOR-1 USING PROPOSED MIXED-FUEL (HEU AND LEU) CORE.

Published in:

Nuclear Technology, 2004, v. 148, n. 3, p. 369, doi. 10.13182/NT04-A3574

By:

Bokhari, Ishtiaq H.

Publication type:

Article

CALCULATIONS OF THE NEUTRON FLUX OUTSIDE BWR 8 x 8 SPENT-FUEL ASSEMBLIES AND THE SENSITIVITY TO FUEL PIN DIVERSION.

Published in:

Nuclear Technology, 2004, v. 146, n. 1, p. 58, doi. 10.13182/NT04-A3487

By:

Jansson, Peter;
Håkansson, Ane;
Bäcklin, Anders

Publication type:

Article

Physical modeling of spent-nuclear-fuel container.

Published in:

China Foundry, 2012, v. 9, n. 4, p. 366

By:

Wang Liping;
Guo Erjun;
Jiang Wenyong;
Xue Muyu;
Liu Dongrong;
Ren Shanzhi

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

India designs new reactor.

Published in:: International Power Generation, 1999, v. 22, n. 7, p. 5
Publication type:: Article

A study on characteristics of end plug resistance welding process in nuclear fuel rods by experiment and numerical simulation.

Published in:

International Journal of Advanced Manufacturing Technology, 2018, v. 98, n. 9-12, p. 2241, doi. 10.1007/s00170-018-2365-3

By:

Na, Tae-Hyung;
Na, Suck-Joo;
Park, Young-Whan

Publication type:

Article

Anisotropy of the conductivity of carbon fibre materials.

Published in:

Fibre Chemistry, 2009, v. 41, n. 6, p. 360, doi. 10.1007/s10692-010-9205-z

By:

Lysenko, V. A.;
Sal'nikova, P. Yu.;
Lysenko, A. A.

Publication type:

Article

Impact of Radiation-Induced Microstructures on the Integrity of Spent Nuclear Fuel (SNF) Elements in Long-Term Storage.

Published in:

Safety of Nuclear Waste Disposal, 2021, v. 1, p. 17, doi. 10.5194/sand-1-17-2021

By:

Yanikömer, Neslihan;
Nabbi, Rahim;
Fischer-Appelt, Klaus

Publication type:

Article

Yield behavior of porous nuclear fuel (UO 2 ).

Published in:

Mechanics of Advanced Materials & Structures, 2016, v. 23, n. 10, p. 1149, doi. 10.1080/15376494.2015.1059529

By:

Aravindan, S.;
Jalaldeen, S.;
Chellapandi, P.;
Swaminathan, N.

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

The Use of a National Nuclear Forensic Library in Order to Identify Unknown Seized Nuclear Material: Brazil's Participation in the Galaxy Serpent Exercise.

Published in:

Journal of the Institute of Nuclear Materials Management, 2014, v. 42, n. 4, p. 24

By:

Souza Sarkis, Jorge Eduardo;
Antunes Costa Bordon, Isabella Cristina;
Baptistini Pestana, Rafael Cardoso;
Coelho Marin, Rafael

Publication type:

Article

U and Pu Isotopic Correlations to Check Consistency of Seized Nuclear Material Against a Known Inventory: Team Sweden Effort to Create and Use a Virtual National Nuclear Forensic Library (NNFL) in the Galaxy Serpent Tabletop Exercise.

Published in:

Journal of the Institute of Nuclear Materials Management, 2014, v. 42, n. 4, p. 70

By:

Axelsson, Anders;
Ramebäck, Henrik;
Sandström, Björn

Publication type:

Article

Galaxy Serpent Virtual Tabletop Exercise: Canada's Approach, Findings, and Lessons Learned.

Published in:

Journal of the Institute of Nuclear Materials Management, 2014, v. 42, n. 4, p. 31

By:

El-Jaby, Ali;
Kosierb, Rick;
Dimayuga, Ike;
Edwards, Geoff;
Barber, Duncan;
Corbett, Stavros;
Wojtaszek, Daniel;
Doucet, François

Publication type:

Article

Development of Analytical Instruments for Prediction of Nuclear Terrorist Activities.

Published in:

Journal of the Institute of Nuclear Materials Management, 2012, v. 40, n. 2, p. 25

By:

Andryushin, Ivan I.;
Varseev, Eugeny V.;
Pshakin, Gennady M.

Publication type:

Article

Evaluating Advanced Fuel Cycle Proliferation Resistance Dynamics Using Isotopic Characterization Coupling.

Published in:

Journal of the Institute of Nuclear Materials Management, 2011, v. 40, n. 1, p. 20

By:

Skutnik, Steven E.;
Yim, Man-Sung

Publication type:

Article

CALCULATIONS OF THE NUCLIDE COMPOSITION OF SPENT NUCLEAR FUEL RBMK-1000 FOR VERIFICATION COMPUTER MODULE SCALE-6.

Published in:

Nuclear Physics & Atomic Energy, 2013, v. 14, n. 4, p. 367

By:

Soloviov, V. V.;
Lebedev, E. O.

Publication type:

Article

Introducing Textiles as Material of Construction of Ethanol Bioreactors.

Published in:

Energies (19961073), 2014, v. 7, n. 11, p. 7555, doi. 10.3390/en7117555

By:

Osadolor, Osagie A.;
Lennartsson, Patrik R.;
Taherzadeh, Mohammad J.

Publication type:

Article

A Procedure to Address the Fuel Rod Failures during LB-LOCA Transient in Atucha-2 NPP.

Published in:

Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/929358

By:

Adorni, Martina;
Del Nevo, Alessandro;
D'Auria, Francesco;
Mazzantini, Oscar

Publication type:

Article

Method for the Calculation of DPA in the Reactor Pressure Vessel of Atucha II.

Published in:

Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/534689

By:

Mascitti, J. A.;
Madariaga, M.

Publication type:

Article

Starting Point, Keys and Milestones of a Computer Code for the Simulation of the Behaviour of a Nuclear Fuel Rod.

Published in:

Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/326948

By:

Marino, Armando C.

Publication type:

Article

A New Fuel Design for Two Different HW Type Reactors.

Published in:

Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/194650

By:

Brasnarof, Daniel O.;
Marino, Armando C.;
Bergallo, Juan E.;
Juanicó, Luis E.

Publication type:

Article

Conceptual Engineering of CARA Fuel Element with Negative Void Coefficient for Atucha II.

Published in:

Science & Technology of Nuclear Installations, 2011, v. 2011, p. 1, doi. 10.1155/2011/264235

By:

Lestani, H.;
Florido, P.;
González, J.

Publication type:

Article

Fission Product Transport and Source Terms in HTRs: Experience from AVR Pebble Bed Reactor.

Published in:

Science & Technology of Nuclear Installations, 2008, v. 2008, p. 1, doi. 10.1155/2008/597491

By:

Moormann, Rainer

Publication type:

Article

RBMK-1500 šilumą išskiriančiuose elementuose vykstančių procesų modeliavimas.

Published in:

Energetika, 2007, n. 4, p. 58

By:

Jusevičiūtė, Aušra;
Kaliatka, Algirdas;
Urbonavičius, Egidijus

Publication type:

Article

INVESTIGATION OF EFFECT OF BALLOONED FUEL PINS ON QUENCHING BEHAVIOR: DESIGN OF EXPERIMENT AND PRELIMINARY ANALYSIS.

Published in:

Nuclear Technology, 2015, v. 190, n. 1, p. 52, doi. 10.13182/NT14-31

By:

GOKHALE, O. S.;
PURANIK, B. P.;
GHOSH, A. K.

Publication type:

Article

UNCERTAINTY ANALYSIS ON REACTIVITY AND DISCHARGED INVENTORY DUE TO <sup>235,238</sup>U, <sup>239,240,241</sup>Pu, AND FISSION PRODUCTS: APPLICATION TO A PRESSURIZED WATER REACTOR FUEL ASSEMBLY.

Published in:

Nuclear Technology, 2014, v. 185, n. 2, p. 174, doi. 10.13182/NT12-154

By:

CRUZ, D. F. DA;
ROCHMAN, D.;
KONING, A. J.

Publication type:

Article

EXPERIMENTAL VALIDATION OF THE DARWIN2.3 PACKAGE FOR FUEL CYCLE APPLICATIONS.

Published in:

Nuclear Technology, 2013, v. 184, n. 2, p. 217, doi. 10.13182/NT12-121

By:

SAN-FELICE, L.;
ESCHBACH, R.;
BOURDOT, P.

Publication type:

Article

THERMAL-HYDRAULIC ANALYSIS FOR HEU AND LEU TRANSITIONAL CORE CONVERSION OF THE MIT RESEARCH REACTOR.

Published in:

Nuclear Technology, 2013, v. 182, n. 3, p. 315, doi. 10.13182/NT12-81

By:

SUNG JOONG KIM;
LIN-WEN HU;
DUNN, FLOYD

Publication type:

Article

FABRICATION OF (U-Pu) MIXED-OXIDE FUEL FOR PRESSURIZED HEAVY WATER REACTORS.

Published in:

Nuclear Technology, 2012, v. 179, n. 2, p. 189, doi. 10.13182/NT12-A14091

By:

Panakkal, J. P.;
Afzal, M.;
Bhatt, R. B.;
Prakash, A.;
Mishra, A. K.;
Kumar, S.;
Kamath, H. S.

Publication type:

Article

LABORATORY TESTS OF AN ULTRASONIC INSPECTION TECHNIQUE TO IDENTIFY DEFECTIVE CANDU FUEL ELEMENTS.

Published in:

Nuclear Technology, 2011, v. 176, n. 3, p. 452, doi. 10.13182/NT11-A13320

By:

Huang, W. H.;
Krause, T. W.;
Lewis, B. J.

Publication type:

Article

DEVELOPMENT OF THE FISSION PRODUCT RELEASE ANALYSIS CODE COPA-FPREL.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 231, doi. 10.13182/NT10-A9461

By:

YOUNG MIN KIM;
MOON SUNG CHO

Publication type:

Article

COMPARISON OF THE HIGH-TEMPERATURE STEAM OXIDATION KINETICS OF ADVANCED CLADDING MATERIALS.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 272, doi. 10.13182/NT10-A9464

By:

GROSSE, M.

Publication type:

Article

RADIONUCLIDE INVENTORY CALCULATIONS FOR THE MATERIALS TEST STATION.

Published in:

Nuclear Technology, 2009, v. 168, n. 3, p. 957, doi. 10.13182/NT09-A9333

By:

KELSEY IV, CHARLES T.;
MUHRER, GUENTER;
PITCHER, ERIC J.

Publication type:

Article

DISMANTLEMENT OF THE TSF-SNAP REACTOR ASSEMBLY.

Published in:

Nuclear Technology, 2009, v. 166, n. 3, p. 252, doi. 10.13182/NT09-A8839

By:

PERETZ, FRED J.

Publication type:

Article

INTEGRATED EFFICIENCY TEST FOR PYROCHEMICAL FUEL CYCLES.

Published in:

Nuclear Technology, 2009, v. 166, n. 2, p. 180, doi. 10.13182/NT09-A7404

By:

LI, S. X.;
VADEN, D.;
WESTPHAL, B. R.;
FREDERICKSON, G. L.;
BENEDICT, R. W.;
JOHNSON, T. A.

Publication type:

Article

BEHAVIOR OF A DEFECTIVE NUCLEAR FUEL ROD IN DRY STORAGE CONDITIONS STUDIED WITH A NEW EXPERIMENTAL SETUP.

Published in:

Nuclear Technology, 2008, v. 163, n. 2, p. 252, doi. 10.13182/NT08-A3985

By:

DESGRANGES, L.;
FERROUD-PLATTET, M. P.;
ALLONCLE, R.;
AUBRUN, I.;
UNTRAU, J. M.;
LHUILLERY, P.

Publication type:

Article

USE OF FUEL ASSEMBLY/BACKFILL GAS EFFECTIVE THERMAL CONDUCTIVITIES TO PREDICT BASKET AND FUEL CLADDING TEMPERATURES WITHIN A RAIL PACKAGE DURING NORMAL TRANSPORT.

Published in:

Nuclear Technology, 2007, v. 160, n. 3, p. 325, doi. 10.13182/NT07-A3903

By:

Greiner, Miles;
Gangadharan, Kishore Kumar;
Gudipati, Mithun

Publication type:

Article