Works matching DE "LIGHT water reactors"

Results: 344

Westinghouse Churchill Hot Cell Facility and Capabilities: Westinghouse Churchill Hot Cell Facility and Capabilities: Clement, Cmar, Hall, Parsi, and Lyons.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2025, v. 77, n. 3, p. 1315, doi. 10.1007/s11837-024-06953-0

By:

Clement, Caleb;
Cmar, Catherine;
Hall, J. Brian;
Parsi, Arash;
Lyons, John

Publication type:

Article

Enhanced Mechanical Properties and Wear Resistance of FeCrAl Alloys at ~ 300°C and Higher Temperatures.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2024, v. 76, n. 8, p. 4123, doi. 10.1007/s11837-024-06540-3

By:

Dolley, Evan J.;
Zhang, Wanming;
Zorn, Gilad;
Sand, Tommy;
Rebak, Raul B.

Publication type:

Article

Localized Helium Implantation in SiCf/SiCm Composites Comparing Fiber and Matrix Swelling.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2020, v. 72, n. 1, p. 170, doi. 10.1007/s11837-019-03869-y

By:

Ambat, M. V.;
Frazer, D.;
Popovic, M. P.;
Balooch, M.;
Stevenson, S.;
Scott, A.;
Kabel, J.;
Hosemann, P.

Publication type:

Article

Ceramic Materials for Nuclear Energy Applications.

Published in:

2019

By:

Zhang, Yongfeng;
Bai, Xian-Ming

Publication type:

Editorial

Correction to: Development of Cold Spray Coatings for Accident-Tolerant Fuel Cladding in Light Water Reactors.

Published in:

2018

By:

Maier, Benjamin;
Yeom, Hwasung;
Johnson, Greg;
Dabney, Tyler;
Walters, Jorie;
Romero, Javier;
Shah, Hemant;
Xu, Peng;
Sridharan, Kumar

Publication type:

Erratum

Laser and Pressure Resistance Weld of Thin-Wall Cladding for LWR Accident-Tolerant Fuels.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2018, v. 70, n. 2, p. 192, doi. 10.1007/s11837-017-2697-8

By:

Gan, J.;
Jerred, N.;
Perez, E.;
Haggard, D. C.

Publication type:

Article

Accident Tolerant Nuclear Fuels and Cladding Materials.

Published in:

2018

By:

Charit, Indrajit

Publication type:

Editorial

CASL Structural Mechanics Modeling of Grid-to-Rod Fretting (GTRF).

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2016, v. 68, n. 11, p. 2922, doi. 10.1007/s11837-016-2095-7

By:

Lu, Wei;
Thouless, M.;
Hu, Zupan;
Wang, Hai;
Ghelichi, Ramin;
Wu, Chen-Hung;
Kamrin, Ken;
Parks, David

Publication type:

Article

Understanding the Atomic-Level Chemistry and Structure of Oxide Deposits on Fuel Rods in Light Water Nuclear Reactors Using First Principles Methods.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2016, v. 68, n. 11, p. 2912, doi. 10.1007/s11837-016-2102-z

By:

Rak, Zs.;
O'Brien, C.;
Brenner, D.;
Andersson, D.;
Stanek, C.

Publication type:

Article

Modeling of Complex Wear Behavior Associated with Grid-to-Rod Fretting in Light Water Nuclear Reactors.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2016, v. 68, n. 11, p. 2938, doi. 10.1007/s11837-016-2113-9

By:

Blau, P.;
Qu, J.;
Lu, R.

Publication type:

Article

Multi-Dimensional Simulation of LWR Fuel Behavior in the BISON Fuel Performance Code.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2016, v. 68, n. 11, p. 2930, doi. 10.1007/s11837-016-2115-7

By:

Williamson, R.;
Capps, N.;
Liu, W.;
Rashid, Y.;
Wirth, B.

Publication type:

Article

Thermal Aging Phenomena in Cast Duplex Stainless Steels.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2016, v. 68, n. 2, p. 507, doi. 10.1007/s11837-015-1709-9

By:

Byun, T.;
Yang, Y.;
Overman, N.;
Busby, J.

Publication type:

Article

Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2016, v. 68, n. 2, p. 517, doi. 10.1007/s11837-015-1753-5

By:

Tan, L.;
Stoller, R.;
Field, K.;
Yang, Y.;
Nam, H.;
Morgan, D.;
Wirth, B.;
Gussev, M.;
Busby, J.

Publication type:

Article

Corrosion and Corrosion Control in Light Water Reactors.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2013, v. 65, n. 8, p. 1043, doi. 10.1007/s11837-013-0658-4

By:

Gordon, Barry

Publication type:

Article

Recent Results of Microstructural Characterization of Irradiated Light Water Reactor Fuels using Scanning and Transmission Electron Microscopy.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2012, v. 64, n. 12, p. 1390, doi. 10.1007/s11837-012-0483-1

By:

Wiss, T.;
Thiele, H.;
Janssen, A.;
Papaioannou, D.;
Rondinella, V.;
Konings, R.

Publication type:

Article

Transient Testing of Nuclear Fuels and Materials in the United States.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2012, v. 64, n. 12, p. 1396, doi. 10.1007/s11837-012-0482-2

By:

Wachs, Daniel

Publication type:

Article

Thermal conductivity of UO fuel: Predicting fuel performance from simulation.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2011, v. 63, n. 8, p. 73, doi. 10.1007/s11837-011-0143-x

By:

Phillpot, Simon R.;
El-Azab, Anter;
Chernatynskiy, Aleksandr;
Tulenko, James S.

Publication type:

Article

Light water reactor fuel performance modeling and multi-dimensional simulation.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2011, v. 63, n. 8, p. 81, doi. 10.1007/s11837-011-0144-9

By:

Rashid, Joseph Y. R.;
Yagnik, Suresh K.;
Montgomery, Robert O.

Publication type:

Article

CASL virtual reactor predictive simulation: Grid-to-Rod Fretting wear.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2011, v. 63, n. 8, p. 53, doi. 10.1007/s11837-011-0139-6

By:

Lu, Roger Y.;
Karoutas, Zeses;
Sham, T.-L.

Publication type:

Article

Light water reactor fuel performance: Current status, challenges, and future high fidelity modeling.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2011, v. 63, n. 8, p. 49, doi. 10.1007/s11837-011-0138-7

By:

Edsinger, K.;
Stanek, C. R.;
Wirth, B. D.

Publication type:

Article

Perspective on modeling light water reactor fuel performance.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2011, v. 63, n. 8, p. 48, doi. 10.1007/s11837-011-0137-8

By:

Wirth, B. D.;
Stanek, C. R.;
Edsinger, K.

Publication type:

Article

Radiation damage concerns for extended light water reactor service.

Published in:

JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2009, v. 61, n. 7, p. 29, doi. 10.1007/s11837-009-0099-2

By:

Allen, T. R.;
Busby, J. T.

Publication type:

Article

Contribution of research to the understanding and mitigation of environmentally assisted cracking in structural components of light water reactors.

Published in:

Corrosion Engineering, Science & Technology, 2018, v. 53, n. 1, p. 11, doi. 10.1080/1478422X.2017.1362158

By:

Tice, David

Publication type:

Article

Corrosion monitoring techniques for detection of crack initiation under simulated light water reactor conditions.

Published in:

Corrosion Engineering, Science & Technology, 2012, v. 47, n. 4, p. 251, doi. 10.1179/1743278212Y.0000000008

By:

Ritter, S;
Horner, D A;
Bosch, R-W

Publication type:

Article

Isotopically modified molybdenum for safe nuclear power.

Published in:

Theoretical Foundations of Chemical Engineering, 2016, v. 50, n. 6, p. 1049, doi. 10.1134/S0040579516060154

By:

Shmelev, A.;
Smirnov, A.;
Bonarev, A.;
Borisevich, V.;
Kulikov, G.;
Sulaberidze, G.

Publication type:

Article

Corrosion behavior of additively manufactured FeCrAl in out-of-pile light water reactor environments.

Published in:

NPJ Materials Degradation, 2024, v. 8, n. 1, p. 1, doi. 10.1038/s41529-024-00499-x

By:

Umretiya, Rajnikant V.;
Qu, Haozheng;
Yin, Liang;
Jurewicz, Timothy B.;
Gupta, Vipul K.;
Drobnjak, Marija;
Knussman, Michael P.;
Hoffman, Andrew K.;
Rebak, Raul B.

Publication type:

Article

Using effective temperature as a measure of the thermal scattering law uncertainties to UOX fuel calculations from room temperature to 80°C.

Published in:

EPJ Nuclear Sciences & Technologies, 2022, v. 8, p. 1, doi. 10.1051/epjn/2022034

By:

Noguere, Gilles;
Xu, Shuqi

Publication type:

Article

Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation.

Published in:

EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2019058

By:

Garbil, R.;
Davies, C.;
Diaconu, D.;
Le Gall, Claire;
Audubert, Fabienne;
Léchelle, Jacques;
Pontillon, Yves;
Hazemann, Jean-Louis

Publication type:

Article

Uncertainty propagation based on correlated sampling technique for nuclear data applications.

Published in:

EPJ Nuclear Sciences & Technologies, 2020, v. 6, p. 1, doi. 10.1051/epjn/2020003

By:

Laureau, Axel;
Lamirand, Vincent;
Rochman, Dimitri;
Pautz, Andreas

Publication type:

Article

Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations.

Published in:

EPJ Nuclear Sciences & Technologies, 2017, v. 3, p. 1, doi. 10.1051/epjn/2017015

By:

Rocchi, Federico;
Guglielmelli, Antonio;
Castelluccio, Donato Maurizio;
Massimi, Cristian

Publication type:

Article

SPECIFIC AND EQUIVALENT CONDUCTIVITY OF DILUTE SODIUM HYDROGEN SELENITE SOLUTIONS IN ORDINARY WATER.

Published in:

Management & Education / Upravlenie i Obrazovanie, 2013, v. 9, n. 6, p. 62

By:

Tavlieva, Mariana;
Georgieva, Velyana;
Genieva, Svetlana

Publication type:

Article

Synthesis of I-131 labelled iodine species relevant during severe nuclear accidents in light water reactors.

Published in:

Radiochimica Acta, 2013, v. 101, n. 10, p. 675, doi. 10.1524/ract.2013.2070

By:

Tietze, S.;
Foreman, M. R. St. J.;
Ekberg, C.

Publication type:

Article

In vessel corium propagation sensitivity study of reactor pressure vessel rupture time with PROCOR platform.

Published in:

Journal of Power Technologies, 2017, v. 97, n. 2, p. 110

By:

Skrzypek, Eleonora;
Skrzypek, Maciej;
Saas, Laurent;
LeTellier, Romain

Publication type:

Article

Passive Residual Heat Removal Systems for Current and Future Light Water Reactors.

Published in:

International Review of Mechanical Engineering, 2015, v. 9, n. 5, p. 466, doi. 10.15866/ireme.v9i5.7143

By:

Dongmei Zhou;
Treleaven, Ian

Publication type:

Article

COMSOL Simulation for Design of Induction Heating System in VULCAN Facility.

Published in:

Science & Technology of Nuclear Installations, 2021, p. 1, doi. 10.1155/2021/9922503

By:

Min, Jinkun;
Zhu, Guangyu;
Yuan, Yidan;
Liu, Jingquan

Publication type:

Article

Study on the Sensitivity and Uncertainty of Nuclear Data to the Sodium-Cooled Linear Breed-and-Burn Fast Reactor Using SCALE6.2 Code.

Published in:

Science & Technology of Nuclear Installations, 2021, p. 1, doi. 10.1155/2021/9997867

By:

Vu, Thanh Mai;
Hartanto, Donny

Publication type:

Article

Best-Estimate Plus Uncertainty Framework for Multiscale, Multiphysics Light Water Reactor Core Analysis.

Published in:

Science & Technology of Nuclear Installations, 2020, p. 1, doi. 10.1155/2020/7526864

By:

Hou, Jason;
Avramova, Maria;
Ivanov, Kostadin

Publication type:

Article

Temperature Profile Measurement in Simulated Fuel Assembly Structure with Wire-Mesh Technology.

Published in:

Science & Technology of Nuclear Installations, 2018, p. 1, doi. 10.1155/2018/2631084

By:

Takiguchi, Hiroki;
Furuya, Masahiro;
Arai, Takahiro

Publication type:

Article

In-Vessel and Ex-Vessel Corium Stabilization in Light Water Reactor.

Published in:

Science & Technology of Nuclear Installations, 2018, p. 1, doi. 10.1155/2018/3918150

By:

Kim, Hwan Yeol;
Bechta, Sevostian;
Foit, Jerzy;
Hong, Seong Wan

Publication type:

Article

Safety Features of High Temperature Gas Cooled Reactor.

Published in:

2017

By:

Fang, Chao;
Morris, Robert;
Li, Fu

Publication type:

Editorial

Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code.

Published in:

Science & Technology of Nuclear Installations, 2017, p. 1, doi. 10.1155/2017/4762709

By:

Yousif, Eltayeb;
Zhang, Zhijian;
Tian, Zhaofei;
Ju, Hao-ran

Publication type:

Article

Radiation Protection Practices during the Helium Circulator Maintenance of the 10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10).

Published in:

Science & Technology of Nuclear Installations, 2016, p. 1, doi. 10.1155/2016/5967831

By:

Guo, Chengxiang;
Wei, Liqiang;
Li, Hong;
Cao, Jianzhu;
Fang, Sheng

Publication type:

Article

Discussion.

Published in:

Journal of Quality Technology, 2000, v. 32, n. 1, p. 28, doi. 10.1080/00224065.2000.11979967

By:

Johnson, Mark E.

Publication type:

Article

Dynamics of lysozyme and its hydration water under an electric field.

Published in:

Journal of Biological Physics, 2014, v. 40, n. 2, p. 167, doi. 10.1007/s10867-014-9343-2

By:

Favi, P.;
Zhang, Q.;
O'Neill, H.;
Mamontov, E.;
Diallo, S.

Publication type:

Article

Enhancement of random sampling by a combined approach of control variates and Latin hypercube sampling for uncertainty quantification in light water reactor lattice calculations.

Published in:

Journal of Nuclear Science & Technology, 2025, v. 62, n. 5, p. 470, doi. 10.1080/00223131.2024.2448320

By:

Fujita, Tatsuya

Publication type:

Article

EPMA and EBSD observations of unirradiated MIMAS-MOX fuels for the study of fission gas release and thermal conductivity.

Published in:

Journal of Nuclear Science & Technology, 2025, v. 62, n. 4, p. 341, doi. 10.1080/00223131.2024.2429803

By:

Kitano, Koji;
Akiyama, Hidetoshi;
Ohishi, Yuji;
Muta, Hiroaki

Publication type:

Article

Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations.

Published in:

Journal of Nuclear Science & Technology, 2024, v. 61, n. 8, p. 1048, doi. 10.1080/00223131.2023.2293106

By:

Abe, Takumi;
Nishihara, Kenji

Publication type:

Article

Techno‐Economic analysis of alternative power cycles for Light‐Water small modular reactors.

Published in:

International Journal of Energy Research, 2022, v. 46, n. 14, p. 19467, doi. 10.1002/er.8516

By:

Kissick, Sean M.;
Wang, Hailei

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

Initial core design analysis of lead (208) ‐bismuth eutectic‐cooled reactor with radial fuel shuffling.

Published in:

International Journal of Energy Research, 2021, v. 45, n. 8, p. 12317, doi. 10.1002/er.6476

By:

Widiawati, Nina;
Su'ud, Zaki;
Irwanto, Dwi;
Permana, Sidik;
Takaki, Naoyuki;
Sekimoto, Hiroshi

Publication type:

Article