Works matching DE "NUCLEAR fuel rods"

Results: 264

Investigation of UO2 fuel efficiency for ABV small modular reactor.

Published in:

Energy Sources Part A: Recovery, Utilization & Environmental Effects, 2025, v. 47, n. 1, p. 10509, doi. 10.1080/15567036.2021.1967516

By:

Karimi, Javad;
Shayesteh, Mohsen;
Zangian, Mehdi

Publication type:

Article

Features of the coolant flow in a fuel rod bundle of the fuel assembly for the RITM-200S reactor of a modernized floating power unit.

Published in:

Atomic Energy, 2025, v. 137, n. 3, p. 161, doi. 10.1007/s10512-025-01190-3

By:

Dmitriev, S. M.;
Demkina, T. D.;
Dobrov, A. A.;
Doronkov, D. V.;
Pronin, A. N.;
Ryazanov, A. V.

Publication type:

Article

Coarse-Grid-CFD for the Thermal Hydraulic Investigation of Rod-Bundles.

Published in:

PAMM: Proceedings in Applied Mathematics & Mechanics, 2015, v. 15, n. 1, p. 497, doi. 10.1002/pamm.201510239

By:

Viellieber, Mathias;
Class, Andreas

Publication type:

Article

Effect of nuclear radiation on the microhardness of SAV-1 avials.

Published in:

Strength of Materials, 2011, v. 43, n. 1, p. 109, doi. 10.1007/s11223-011-9274-0

By:

Abdukadyrova, I.;
Tadzhibaev, D.

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

THERMAL TECHNOLOGICAL CONDITION OF IVG.1M RESEARCH REACTOR CORE UNDER VARIOUS OPERATING MODES.

Published in:

Eurasian Physical Technical Journal, 2024, v. 21, n. 3, p. 45, doi. 10.31489/2024No3/45-53

By:

Skakov, M. K.;
Martynenko, Ye. A.;
Yerdybayeva, N. K.;
Akayev, A. S.;
Bekmuldin, M. K.;
Prozorova, I. V.

Publication type:

Article

LONG-TERM FAILURE OF DYNAMIC RODS USED IN FULL DYNAMIC STABILIZATION.

Published in:

Journal of Turkish Spinal Surgery, 2023, v. 34, n. 4, p. 137, doi. 10.4274/jtss.galenos.2023.68077

By:

Akgün, Mehmet Yiğit;
Ateş, Özkan;
Günerbüyük, Caner;
Karadağ, Mehmet Kürşat;
Özer, Ali Fahir

Publication type:

Article

Three dimensional steady‐state neutronics/thermal‐hydraulics coupled simulation for a molten salt reactor moderated by zirconium hydride rods.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 12358, doi. 10.1002/er.6534

By:

Zhu, Fan;
Deng, Bin;
Wu, Jianhui;
Yu, Chenggang;
Chen, Jingen;
Cai, Xiangzhou

Publication type:

Article

Fuel breeding and waste burnup capabilities of an accelerator‐driven system using thorium and reprocessed fuels.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 11882, doi. 10.1002/er.5886

By:

Barros, Graiciany;
Campagnole dos Santos, Andre A.;
Vasconcelos, Vitor;
Campolina, Daniel;
Pereira, Claubia

Publication type:

Article

Parametric study on minor actinides transmutation in a graphite‐moderated thorium‐based molten salt reactors.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 5, p. 7840, doi. 10.1002/er.6368

By:

Zou, Chunyan;
Yu, Chenggang;
Wu, Jianhui;
Cai, Xiangzhou;
Chen, Jingen

Publication type:

Article

Analysis of temperature distribution, burn-up and breeding parameters in nuclear fuel rod in fusion-fission reactor system fueled with mixed ThO.

Published in:

International Journal of Energy Research, 2011, v. 35, n. 2, p. 112, doi. 10.1002/er.1771

By:

İpek, Osman

Publication type:

Article

توسعه مدل عددی میله سوخت مجازی تحت شبکه‌های نگهدارنده‌ جدید و قیدهای انتهایی به کمک تحلیل تجربی مودال.

Published in:

Journal of Applied & Computational Sciences in Mechanics, 2022, v. 34, n. 4, p. 89, doi. 10.22067/JACSM.2022.75471.1103

By:

رضا امیریان;
غلامرضا زارع پور;
منصور طالبی

Publication type:

Article

South Korea in focus: The politics of spent fuel storage and disposal.

Published in:

Bulletin of the Atomic Scientists, 2011, v. 67, n. 3, p. 51, doi. 10.1177/0096340211407146

By:

Kang, Jungmin

Publication type:

Article

Changing the way water boils on surfaces.

Published in:

New Mexico Journal of Science, 2018, v. 52, n. 1, p. 53

By:

CVIJOVIC, LAZAR

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

Water Model Experiments on the Influence of Phase Distribution in the Submerged Entry Nozzle Considering Varying Operating Conditions.

Published in:

Steel Research International, 2022, v. 93, n. 12, p. 1, doi. 10.1002/srin.202100824

By:

Thumfart, Maria;
Hackl, Gernot;
Fellner, Wolfgang

Publication type:

Article

An assessment of delayed hydride cracking in zirconium alloy cladding tubes under stress transients.

Published in:

International Materials Reviews, 2013, v. 58, n. 6, p. 349, doi. 10.1179/1743280412Y.0000000013

By:

Chan, K S

Publication type:

Article

ANALYSIS OF THE BUBBLY-CHURN REGIME TRANSITION IN A SCALED MODEL BOILING WATER REACTOR.

Published in:

Nuclear Technology, 2006, v. 154, n. 3, p. 328, doi. 10.13182/NT06-A3737

By:

Meftah, Khaled;
Ruggles, Arthur E.

Publication type:

Article

AN ASSESSMENT OF FUEL DAMAGE IN POSTULATED REACTIVITY-INITIATED ACCIDENTS.

Published in:

Nuclear Technology, 2006, v. 155, n. 3, p. 293, doi. 10.13182/NT06-A3763

By:

Meyer, Ralph O.

Publication type:

Article

ANALYSIS OF PELLET-CLAD MECHANICAL INTERACTION PROCESS OF HIGH-BURNUP PWR FUEL RODS BY RANNS CODE IN REACTIVITY-INITIATED ACCIDENT CONDITIONS.

Published in:

Nuclear Technology, 2006, v. 155, n. 3, p. 282, doi. 10.13182/NT06-A3762

By:

Suzuki, Motoe;
Fuketa, Toyoshi;
Saitou, Hiroaki

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

BALLOONING EXPERIMENTS WITH VVER CLADDING.

Published in:

Nuclear Technology, 2005, v. 152, n. 3, p. 273

By:

Hózer, Zoltán;
Győri, Csaba;
Horváth, Márta;
Nagy, Imre;
Maróti, László;
Matus, Lajos;
Windberg, Péter;
Frecska, József

Publication type:

Article

PERFORMANCE OF A CLAD TUNGSTEN ROD SPALLATION NEUTRON SOURCE TARGET.

Published in:

Nuclear Technology, 2005, v. 151, n. 3, p. 303, doi. 10.13182/NT05-A3653

By:

Sommer, Walter F.;
Maloy, Stuart A.;
Louthan, McIntyre R.;
Willcutt, Gordon J.;
Ferguson, Phillip D.;
James, Michael R.

Publication type:

Article

ASSESSMENT OF THE RANS TURBULENCE MODELS FOR A TURBULENT FLOW AND HEAT TRANSFER IN A ROD BUNDLE.

Published in:

Nuclear Technology, 2005, v. 150, n. 3, p. 231, doi. 10.13182/NT05-A3619

By:

Wang-Nee In;
Tae-Hyun Chun

Publication type:

Article

A NEW APPARATUS FOR DETERMINATION OF THE FREE VOLUME OF A FUEL ROD USING THE DOUBLE EXPANSION METHOD.

Published in:

Nuclear Technology, 2005, v. 149, n. 1, p. 14, doi. 10.13182/NT05-A3576

By:

Desgranges, Lionel;
Faure, Marie-Hèlene;
Thouroude, Alain

Publication type:

Article

HYDROGEN GENERATION IN REFLOODING EXPERIMENTS WITH LWR-TYPE ROD BUNDLES (QUENCH PROGRAM).

Published in:

Nuclear Technology, 2004, v. 147, n. 2, p. 202, doi. 10.13182/NT04-A3526

By:

Sepold, Leo K.;
Miassoedov, Alexei;
Schanz, Gerhard;
Stegmaier, Ulrike;
Steinbrück, Martin;
Stuckert, Juri;
Homann, Christoph

Publication type:

Article

MULTILEVEL METHODOLOGY IN PARALLEL COMPUTING ENVIRONMENT FOR EVALUATING BWR SAFETY PARAMETERS.

Published in:

Nuclear Technology, 2004, v. 146, n. 3, p. 267, doi. 10.13182/NT04-A3505

By:

Solís, Jorge;
Avramova, Maria N.;
Ivanov, Kostadin N.

Publication type:

Article

A NEURAL NETWORK MODEL FOR THE TOMOGRAPHIC ANALYSIS OF IRRADIATED NUCLEAR FUEL RODS.

Published in:

Nuclear Technology, 2004, v. 146, n. 1, p. 65, doi. 10.13182/NT04-A3488

By:

Craciunescu, Teddy

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

TECHNOLOGY DEVELOPMENT ISSUES FOR HIGH-CONVERSION BWRs USING ISLAND-TYPE MOX FUEL.

Published in:

Nuclear Technology, 2004, v. 145, n. 3, p. 257, doi. 10.13182/NT04-A3475

By:

Kondo, Takao;
Mochida, Takaaki;
Yamashita, Junichi

Publication type:

Article

ABWR-II CORE DESIGN WITH SPECTRAL SHIFT RODS FOR OPERATION WITH ALL CONTROL RODS WITHDRAWN.

Published in:

Nuclear Technology, 2004, v. 145, n. 3, p. 247, doi. 10.13182/NT04-A3474

By:

Moriwaki, Masanao;
Aoyama, Motoo;
Anegawa, Takafumi;
Okada, Hiroyuki;
Sakurada, Koichi;
Tanabe, Akira

Publication type:

Article

Numerical modeling of pressure resistance welding of zirconium alloy tube-end plug joint.

Published in:

International Journal of Advanced Manufacturing Technology, 2022, v. 121, n. 5/6, p. 3337, doi. 10.1007/s00170-022-09513-5

By:

Feng, Gang;
Lin, Jian;
Yang, Jia;
Liang, Zhenxin;
Lu, Li;
Lei, Yongping;
Fu, Hanguang

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

DETERMINATION OF GRANULOMETRIC COMPOSITION OF TECHNOGENIC RAW MATERIALS FOR PRODUCING COMPOSITE FUEL.

Published in:

Scientific Bulletin of National Mining University, 2022, n. 4, p. 52, doi. 10.33271/nvngu/2022-4/052

By:

Haidai, O. A.;
Pavlychenko, A. V.;
Koveria, А. S.;
Ruskykh, V. V.;
Lampika, T. V.

Publication type:

Article

Interactions Between Gas Slug Ascent and Exchange Flow in the Conduit of Persistently Active Volcanoes.

Published in:

Journal of Geophysical Research. Solid Earth, 2021, v. 126, n. 9, p. 1, doi. 10.1029/2021JB022120

By:

Qin, Zhipeng;
Beckett, Frances M.;
Rust, Alison C.;
Suckale, Jenny

Publication type:

Article

Analysis of Temperature Field Inside the Fuel Rod of the VVER 440 Fuel Assembly.

Published in:

International Review of Mechanical Engineering, 2011, v. 5, n. 2, p. 291

By:

Sačková, Miriama;
Hatala, Branislav;
Nečas, Vladimír

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

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

Algorithm development for quality monitoring on end plug resistance weldment of nuclear fuel rods.

Published in:

International Journal of Advanced Manufacturing Technology, 2016, v. 85, n. 5-8, p. 991, doi. 10.1007/s00170-015-7997-y

By:

Na, Tae-Hyung;
Na, Suck-Joo;
Ko, Mi-Hae;
Hwang, Dong-Soo

Publication type:

Article

State of the art of hydraulic packer testing in clay rocks in the Swiss national radioactive waste disposal program.

Published in:

2023

By:

Dausse, Amélie;
Beauheim, Richard;
Roberts, Randall;
Paris, Benoît;
Cavalera, Thomas;
Croisé, Jean;
Pechstein, Armin

Publication type:

Abstract

Spectroscopic and chemical investigations on volatile fission and activation products within the fuel-cladding interface of irradiated pressurised water reactor fuel rod segments.

Published in:

Safety of Nuclear Waste Disposal, 2021, v. 1, p. 5, doi. 10.5194/sand-1-5-2021

By:

König, Tobias;
Dagan, Ron;
Dardenne, Kathy;
Herm, Michel;
Metz, Volker;
Pruessmann, Tim;
Rothe, Jörg;
Schild, Dieter;
Walschburger, Arndt;
Geckeis, Horst

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 Performance of Self-interrogation Neutron Resonance Densitometry in Measuring Spent Fuel.

Published in:

Journal of the Institute of Nuclear Materials Management, 2012, v. 40, n. 3, p. 36

By:

Jianwei Hu;
Trellue, Holly R.;
Tobin, Stephen J.;
Ulrich, T. J.;
LaFleur, Adrienne M.;
Freeman, Corey R.;
Menlove, Howard O.;
Swinhoe, Martyn T.

Publication type:

Article

Investigations towards incorporation of Eu3+ and Cm3+ during ZrO2 crystallization in aqueous solution.

Published in:

Scientific Reports, 2023, v. 13, n. 1, p. 1, doi. 10.1038/s41598-023-39143-0

By:

Opitz, Lucas;
Hübner, René;
Shams Aldin Azzam, Salim;
Gilson, Sara E.;
Finkeldei, Sarah C.;
Huittinen, Nina

Publication type:

Article

THERMAL HYDRAULIC METHOD OF OPTIMIZING THE THERMAL RESISTANCE OF NUCLEAR FUEL OF REACTOR INSTALLATIONS.

Published in:

Nuclear Physics & Atomic Energy, 2024, v. 25, n. 1, p. 43, doi. 10.15407/jnpae2024.01.043

By:

Skalozubov, V. I.;
Dorozh, O. A.;
Komarov, Yu. O.;
Galatsan, M. P.;
Mazurenko, A. S.;
Bundev, D. S.

Publication type:

Article

THERMAL-HYDRAULIC CALCULATIONS OF THE WWR-SM RESEARCH REACTOR.

Published in:

Nuclear Physics & Atomic Energy, 2020, v. 21, n. 2, p. 152, doi. 10.15407/jnpae2020.02.152

By:

Baytelesov, S. A.;
Kungurov, F. R.;
Yuldashev, B. S.

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

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

Clad Metals: Fabrication, Properties, and Applications.

Published in:

2021

By:

Cho, Young-Rae

Publication type:

Editorial

Development of Equivalent Beam Model of High Burnup Spent Nuclear Fuel Rods under Lateral Impact Loading.

Published in:

Metals (2075-4701), 2020, v. 10, n. 4, p. 470, doi. 10.3390/met10040470

By:

Lee, Sanghoon;
Kim, Seyeon

Publication type:

Article