Works about NUCLEAR fuel rods

Results: 262

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

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

Mathematical modelling of nonlinear vibration and fretting wear of the nuclear fuel rods.

Published in:

Archive of Applied Mechanics, 2016, v. 86, n. 4, p. 657, doi. 10.1007/s00419-015-1053-0

By:

Zeman, Vladimír;
Dyk, Štěpán;
Hlaváč, Zdeněk

Publication type:

Article

US spent-fuel ban leaves European research reactors out in the cold.

Published in:

Nature, 1995, v. 373, n. 6515, p. 547, doi. 10.1038/373547a0

By:

Abbott, Alison

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

Operation of High-Voltage Plasma Torches with Rod Electrodes.

Published in:

High Temperature, 2018, v. 56, n. 6, p. 849, doi. 10.1134/S0018151X1805022X

By:

Safronov, A. A.;
Vasilieva, O. B.;
Dudnik, Yu. D.;
Kuznetsov, V. E.;
Shiryaev, V. N.

Publication type:

Article

Investigation of heat removal in annular channels with swirl and transit flow in the precrisis region.

Published in:

High Temperature, 2016, v. 54, n. 4, p. 519, doi. 10.1134/S0018151X16030032

By:

Boltenko, E.

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

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

Effect of Pu content on uncertainty in reactor parameters due to use of no temperature gradient in (U-Pu)O2 fuels.

Published in:

Turkish Journal of Physics, 2017, v. 41, n. 2, p. 113, doi. 10.3906/fiz-1609-8

By:

TÜRKMEN, Mehmet

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

3x3 ロッドバンドルにおけるフラッデイング状態での流動特性.

Published in:

Japanese Journal of Multiphase Flow, 2021, v. 35, n. 1, p. 159

By:

村瀬道雄;
佐野直樹;
高木俊弥;
合田頼人;
林公祐;
冨山明男

Publication type:

Article

冷却機能喪失時の使用済み燃料プールのスプレイ流入とクエンチ特性.

Published in:

Japanese Journal of Multiphase Flow, 2021, v. 35, n. 1, p. 142

By:

笹川達也;
水谷義隆;
奥井翔大;
河野智美;
久保雄一郎;
片岡勲

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

CAST3M modelling of a spent fuel assembly bending during a handling accident Rod failure risk evaluation from the experimental results of spent fuel rod bending test.

Published in:

Mechanics & Industry, 2014, v. 15, n. 4, p. 301, doi. 10.1051/meca/2014031

By:

GUERIN, C.;
LAPORTE, T.;
CAPPELAERE, C.;
VAILLE, C.;
MONGABURE, P.;
MIQUET, A.;
BOUFFIOUX, P.

Publication type:

Article

Selective extraction of Hf( IV) over Zr( IV) from aqueous H2SO4 solutions by solvent extraction with acidic organophosphorous based extractants.

Published in:

Journal of Chemical Technology & Biotechnology, 2014, v. 89, n. 11, p. 1712, doi. 10.1002/jctb.4249

By:

Banda, Raju;
Min, Soo Hwan;
Lee, Man Seung

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

THE EFFECT OF SUBCOOLED WATER PARAMETERS ON THERMAL-HYDRAULIC CHARACTERISTICS FOR VVER REACTOR.

Published in:

Thermal Science, 2025, v. 29, n. 1A, p. 27, doi. 10.2298/TSCI240330151K

By:

KOROTKIKH, Alexander G.;
ODII, Christopher J.

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

Inspection of nuclear storage tanks using remotely deployed ACFMT.

Published in:

Insight: Non-Destructive Testing & Condition Monitoring, 2007, v. 49, n. 1, p. 17, doi. 10.1784/insi.2007.49.1.17

By:

Smith, M.;
Laenen, C.

Publication type:

Article

Grid supports design for dual-cooled fuel rods.

Published in:

International Journal of Multiphysics, 2011, v. 5, n. 4, p. 299, doi. 10.1260/1750-9548.5.4.299

By:

Kim, JaeYong;
Lee, YoungHo;
Yoon, KyungHo;
Kim, HyungKyu

Publication type:

Article

Madrid's nuclear reactor to be dismantled.

Published in:

Frontiers in Ecology & the Environment, 2005, v. 3, n. 7, p. 352, doi. 10.2307/3868574

By:

Burton, Adrian

Publication type:

Article

Mathematical modelling of friction-vibration interactions of nuclear fuel rods.

Published in:

Applied & Computational Mechanics, 2016, v. 10, n. 1, p. 57

By:

Zeman, V.;
Hlaváč, Z.

Publication type:

Article

Dynamic response of nuclear fuel assembly excited by pressure pulsations.

Published in:

Applied & Computational Mechanics, 2012, v. 6, n. 2, p. 219

By:

Zeman, V.;
Hlaváč, Z.

Publication type:

Article

Modelling and modal properties of nuclear fuel assembly.

Published in:

Applied & Computational Mechanics, 2011, v. 5, n. 2, p. 253

By:

Zeman, V.;
Hlaváč, Z.

Publication type:

Article

SCIENCE.

Published in:: Bulletin of the Atomic Scientists, 1959, v. 15, n. 1, p. 48
Publication type:: Article

CHEMICAL ASPECTS OF THE ATOMIC LNIERGY PROBLEM.

Published in:

Bulletin of the Atomic Scientists, 1949, v. 5, n. 2, p. 48, doi. 10.1080/00963402.1949.11457037

By:

Spedding, F. H.

Publication type:

Article

Flow Measurement Methods in Small Tributaries of the Teles Pires River, Southern of the Amazon Hydrological Region.

Published in:

Water (20734441), 2023, v. 15, n. 21, p. 3811, doi. 10.3390/w15213811

By:

Borella, Daniela Roberta;
Paulista, Rhavel Salviano Dias;
Alves, Marco Aurélio Barbosa;
Martim, Charles Campoe;
da Silva, Célio Jacinto;
de Almeida, Frederico Terra;
de Souza, Adilson Pacheco

Publication type:

Article

Fukushima, Fuel Rods, and the Crisis of Divided and Distracted Governance.

Published in:

Asia-Pacific Journal: Japan Focus, 2013, v. 11, n. 33, p. 2, doi. 10.1017/s1557466013016823

By:

DeWit, Andrew

Publication type:

Article

A Practical Approach to Operational Hydrodynamic Slug Analysis in Pipelines.

Published in:

International Journal of Chemical Reactor Engineering, 2015, v. 13, n. 4, p. 503, doi. 10.1515/ijcre-2014-0159

By:

Galatro, Daniela;
Ercolani, Dario;
Fuertbauer, Daniel

Publication type:

Article

CFD code application: calculating heat transfer in a reactor with supercritical parameters.

Published in:

Atomic Energy, 2012, v. 111, n. 4, p. 252, doi. 10.1007/s10512-012-9485-x

By:

Smirnov, V.;
Papandin, M.;
Loninov, A.;
Vanyukova, G.;
Afonin, S.

Publication type:

Article

Effect of deformation and loss-of-seal on the embrittlement of VVER fuel-element cladding in loss-of-coolant accidents.

Published in:

Atomic Energy, 2008, v. 104, n. 5, p. 355, doi. 10.1007/s10512-008-9040-y

By:

V. Deniskin;
D. Ignat’ev;
V. Konstantinov;
V. Nalivaev;
D. Soldatkin;
I. Fedik

Publication type:

Article

Analysis of damage to RBMK core components as a result of an unanticipated accident.

Published in:

Atomic Energy, 2008, v. 104, n. 4, p. 278, doi. 10.1007/s10512-008-9029-6

By:

V. Tkachev;
D. Mikhailov;
K. Zheltukhin

Publication type:

Article

Numerical investigation of temperature distribution and melt pool geometry in laser beam welding of a Zr–1% Nb alloy nuclear fuel rod end cap.

Published in:

Bulletin of Materials Science, 2019, v. 42, n. 4, p. 1, doi. 10.1007/s12034-019-1873-6

By:

Satyanarayana, G.;
Narayana, K. L.;
Rao, B. Nageswara

Publication type:

Article

BENCHMARK OF COMPUTATIONAL FLUID DYNAMICS SIMULATIONS USING TEMPERATURES MEASURED WITHIN ENCLOSED VERTICAL AND HORIZONTAL ARRAYS OF HEATED RODS.

Published in:

Nuclear Technology, 2009, v. 167, n. 3, p. 371, doi. 10.13182/NT167-371

By:

CHALASANI, N. R.;
ARAYA, PABLO E.;
GREINER, MILES

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

HIGH-POWER-DENSITY ANNULAR FUEL FOR PRESSURIZED WATER REACTORS: MANUFACTURING COSTS AND ECONOMIC BENEFITS.

Published in:

Nuclear Technology, 2007, v. 160, n. 1, p. 112, doi. 10.13182/NT07-A3887

By:

Lahoda, Edward;
Mazzoccoli, Jason;
Beccherle, Julien

Publication type:

Article

HIGH-POWER-DENSITY ANNULAR FUEL: MANUFACTURING VIABILITY.

Published in:

Nuclear Technology, 2007, v. 160, n. 1, p. 100, doi. 10.13182/NT07-A3886

By:

Lahoda, Edward;
Feinroth, Herbert;
Salvatore, Marcelo;
Russo, Diego O.;
Hamilton, Holly

Publication type:

Article

THERMAL-HYDRAULIC DESIGN OF HIGH-POWER-DENSITY ANNULAR FUEL IN PWRs.

Published in:

Nuclear Technology, 2007, v. 160, n. 1, p. 16, doi. 10.13182/NT07-A3882

By:

Feng, Dandong;
Hejzlar, Pavel;
Kazimi, Mujid S.

Publication type:

Article

THE NEAR BOILING REACTOR: DESIGN OF A SMALL, INHERENTLY SAFE, NUCLEAR REACTOR TO EXTEND THE OPERATIONAL ENVELOPE OF THE VICTORIA-CLASS SUBMARINE.

Published in:

Nuclear Technology, 2007, v. 159, n. 1, p. 1

By:

Bonin, Hugues

Publication type:

Article

SUMMARY AND INTERPRETATION OF THE CABRI REP-Na PROGRAM.

Published in:

Nuclear Technology, 2007, v. 157, n. 3, p. 230, doi. 10.13182/NT07-A3815

By:

Papin, J.;
Cazalis, B.;
Frizonnet, J. M.;
Desquines, J.;
Lemoine, F.;
Georgenthum, V.;
Lamare, F.;
Petit, M.

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

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