Works matching DE "NUCLEAR reactor cores"
Results: 423
A Thermal Approach for Modeling Concrete Ablation During Molten Corium–Concrete Interaction.
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- Arabian Journal for Science & Engineering (Springer Science & Business Media B.V. ), 2025, v. 50, n. 5, p. 3317, doi. 10.1007/s13369-024-09377-9
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- Article
Part Strength Control Element Assemblies Effectiveness in APR1400 Reactivity Management During Transient Operation.
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- Arabian Journal for Science & Engineering (Springer Science & Business Media B.V. ), 2025, v. 50, n. 5, p. 3113, doi. 10.1007/s13369-023-08222-9
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- Article
A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors: Examining Homogeneous and Heterogeneous Enrichment Design.
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- Arabian Journal for Science & Engineering (Springer Science & Business Media B.V. ), 2025, v. 50, n. 5, p. 3059, doi. 10.1007/s13369-023-07905-7
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- Article
压水堆控制棒导向筒与堆芯上板间隙 对控制棒落棒时间的影响研究.
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- Nuclear Safety, 2025, v. 24, n. 1, p. 53
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Review of Experimental and Numerical Studies on Critical Heat Flux in China.
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- Energies (19961073), 2025, v. 18, n. 4, p. 781, doi. 10.3390/en18040781
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Methods to overcome embrittlement problem in 9Cr–1Mo ferritic steel and its weldment.
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- Journal of Materials Science, 2009, v. 44, n. 9, p. 2239, doi. 10.1007/s10853-008-3199-4
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Optimization of Core Regions and Fuel Fractions for Better Power Peaking Factor of 150, 450 and 1,000 MWth Molten Salt Reactor.
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- Trends in Sciences, 2023, v. 20, n. 12, p. 1, doi. 10.48048/tis.2023.6937
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- Article
Measurement of the Reactivity Coefficients and Neutron Flux of the SLOWPOKE-2 Reactor Using OpenMC.
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- International Journal on Engineering Applications, 2023, v. 11, n. 4, p. 270, doi. 10.15866/irea.v11i4.23349
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The Method to Predict First Critical Core Loading for Nuclear Reactors.
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- Sakarya University Journal of Science (SAUJS) / Sakarya Üniversitesi Fen Bilimleri Enstitüsü Dergisi, 2020, v. 24, n. 6, p. 1329, doi. 10.16984/saufenbilder.677487
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Eating gamma radiation for breakfast.
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- Biologist, 2023, v. 70, n. 2, p. 12
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Investigation on Neutronic Parameters of the KLT-40S Reactor Core with U<sub>3</sub>Si<sub>2</sub>-FeCrAl using SCALE Code.
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- Journal of Engineering & Technological Sciences, 2023, v. 55, n. 1, p. 22, doi. 10.5614/j.eng.technol.sci.2023.55.1.3
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- Article
Development of TDLAS sensor for diagnostics of CO, HO and soot concentrations in reactor core of pilot-scale gasifier.
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- Applied Physics B: Lasers & Optics, 2016, v. 122, n. 2, p. 1, doi. 10.1007/s00340-016-6319-x
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- Article
Detection of Numerical Power Shift Anomalies in Burnup Modeling of a PWR Reactor.
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- Sustainability (2071-1050), 2023, v. 15, n. 4, p. 3373, doi. 10.3390/su15043373
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- Article
Study on Fuel Selection for a Long-Life Small Lead-Based Reactor.
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- Sustainability (2071-1050), 2022, v. 14, n. 24, p. 16840, doi. 10.3390/su142416840
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- Article
Core Design and Deployment Strategy of Heavy Water Cooled Sustainable Thorium Reactor.
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- Sustainability (2071-1050), 2012, v. 4, n. 8, p. 1933, doi. 10.3390/su4081933
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- Article
RESEARCH ON THE EFFECTS OF LOCAL THROTTLING ON THERMAL-INDUCED TWO-PHASE FLOW INSTABILITIES IN THE TYPICAL COOLANT OPEN-CHANNEL SYSTEM IN THE NUCLEAR REACTOR CORE.
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- Thermal Science, 2022, v. 26, n. 5B, p. 4095, doi. 10.2298/TSCI2205095L
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- Article
THERMAL PERFORMANCE ANALYSIS AND OPTIMIZATION DESIGN OF DRY TYPE AIR CORE REACTOR WITH THE DOUBLE RAIN COVER.
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- Thermal Science, 2022, v. 26, n. 1A, p. 273, doi. 10.2298/TSCI201014067Y
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- Article
Feasibility Study on the Initial Kartini Reactor Core Using Plate Type Fuel Elements.
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- Science & Technology of Nuclear Installations, 2022, p. 1, doi. 10.1155/2022/9629413
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- Article
Event Sequence Based Fault Tree Analysis to Evaluate Minimal Combination of Event Sequences Leading to the Reactor Core Damage.
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- Gazi University Journal of Science, 2024, v. 37, n. 3, p. 1319, doi. 10.35378/gujs.1313692
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- Article
Global risk of radioactive fallout after nuclear reactor accidents.
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- Atmospheric Chemistry & Physics Discussions, 2011, v. 11, n. 11, p. 31207, doi. 10.5194/acpd-11-31207-2011
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- Article
EFFECIENCY OF SIMULATING DECAY HEAT IN THE CORIUM OF A NUCLEAR REACTOR BY THE OHMIC HEATING METHOD.
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- Recent Contributions to Physics, 2024, v. 90, n. 3, p. 108, doi. 10.26577/RCPh.2024v90i3-013
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- Article
車載リアクトル用高密度・低損失圧粉磁心の開発.
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- Journal of the Japan Society of Powder & Powder Metallurgy / Funtai Oyobi Fummatsu Yakin, 2024, v. 71, n. 7, p. 245, doi. 10.2497/jjspm.23-00082
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- Article
Analysis of the Vibration Characteristics and Vibration Reduction Methods of Iron Core Reactor.
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- Actuators, 2023, v. 12, n. 9, p. 365, doi. 10.3390/act12090365
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- Article
An overview of activation cross-section measurements of some neutron and charged-particle induced reactions in Bangladesh.
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- Radiochimica Acta, 2022, v. 110, n. 6-9, p. 663, doi. 10.1515/ract-2021-1092
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- Article
AN OPTIMISATION-BASED DECISION SUPPORT SYSTEM FRAMEWORK FOR MULTI-OBJECTIVE IN-CORE FUEL MANAGEMENT OF NUCLEAR REACTOR CORES.
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- South African Journal of Industrial Engineering, 2016, v. 27, n. 3, p. 201, doi. 10.7166/27-3-1650
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- Article
Assessment of Nutrient Limitation in Floodplain Forests with Two Different Techniques.
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- Research Letters in Ecology, 2008, p. 1, doi. 10.1155/2008/260754
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- Article
Nucleus: Searching for Coherent Neutrino Nucleus Scattering at Lowest Energies.
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- Journal of Low Temperature Physics, 2022, v. 209, n. 5/6, p. 936, doi. 10.1007/s10909-022-02862-1
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- Article
ESTE—DECISION SUPPORT SYSTEM FOR NUCLEAR AND RADIOLOGICAL ACCIDENTS.
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- Radiation Protection Dosimetry, 2019, v. 186, n. 2/3, p. 321, doi. 10.1093/rpd/ncz226
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- Article
Detection of Prompt Gamma Radiation Near the LVR-15 Research Reactor.
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- Radiation Protection Dosimetry, 2019, v. 186, n. 2/3, p. 244, doi. 10.1093/rpd/ncz212
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- Article
RADIATION HAZARDS FROM CRITICALITY ACCIDENT IN OPEN POOL TYPE REACTOR.
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- Radiation Protection Dosimetry, 2019, v. 183, n. 3, p. 336, doi. 10.1093/rpd/ncy122
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- Article
Understanding fracture behaviour of PGA reactor core graphite: perspective.
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- Materials Science & Technology, 2014, v. 30, n. 2, p. 129, doi. 10.1179/1743284713Y.0000000354
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- Article
Fabrication and characterization of an irradiation facility for large-sample geometry.
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- Journal of Radioanalytical & Nuclear Chemistry, 2013, v. 296, n. 1, p. 83, doi. 10.1007/s10967-012-2073-7
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- Article
Coarse-Grid-CFD for the Thermal Hydraulic Investigation of Rod-Bundles.
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- PAMM: Proceedings in Applied Mathematics & Mechanics, 2015, v. 15, n. 1, p. 497, doi. 10.1002/pamm.201510239
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- Article
Coarse-Grid-CFD for a Wire Wrapped Fuel Assembly.
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- PAMM: Proceedings in Applied Mathematics & Mechanics, 2013, v. 13, n. 1, p. 317, doi. 10.1002/pamm.201310154
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- Article
Bir Kaynar Su Reaktör Modellemesinde Np ve Am Yakıt Çubukları için Bazı Nötronik Değerlerin İncelenmesi.
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- Suleyman Demirel University Faculty of Arts & Science Journal of Science / Süleyman Demirel Üniversitesi Fen Edebiyat Fakültesi Fen Dergisi, 2020, v. 15, n. 1, p. 140, doi. 10.29233/sdufeffd.705690
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- Article
Analysis of modern approaches to improve the efficiency of blackout accident management at nuclear power plants.
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- Refrigeration Engineering & Technology, 2019, v. 55, n. 4, p. 227, doi. 10.15673/ret.v55i4.1635
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- Article
干式铁芯电抗器匝间短路故障检测与定位方法.
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- Journal of Harbin University of Science & Technology, 2020, v. 25, n. 6, p. 63, doi. 10.15938/j.jhust.2020.06.009
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- Article
NEUTRONIC ANALYSIS ON MOLTEN SALT REACTOR FUJI-12 USING <sup>235</sup>U AS FISSILE MATERIAL IN LiF-BeF<sub>2</sub>-UF<sub>4</sub> FUEL.
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- Eastern-European Journal of Enterprise Technologies, 2022, v. 119, n. 8, p. 6, doi. 10.15587/1729-4061.2022.265798
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- Article
COMPARISON OF THORIUM NITRIDE AND URANIUM NITRIDE FUEL ON SMALL MODULAR PRESSURIZED WATER REACTOR IN NEUTRONIC ANALYSIS USING SRAC CODE.
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- Eastern-European Journal of Enterprise Technologies, 2022, v. 116, n. 8, p. 21, doi. 10.15587/1729-4061.2022.255849
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- Article
Investigation on pressure pulsation and modal behavior of the impeller in a nuclear reactor coolant pump.
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- Energy Science & Engineering, 2021, v. 9, n. 9, p. 1440, doi. 10.1002/ese3.904
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- Article
Long-time irradiation effect on corrosion behavior of aluminum alloy in pool water of low-power research reactor.
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- Scientific Reports, 2023, v. 13, n. 1, p. 1, doi. 10.1038/s41598-023-44287-0
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- Article
Long-time irradiation effect on corrosion behavior of aluminum alloy in pool water of low-power research reactor.
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- Scientific Reports, 2023, v. 13, n. 1, p. 1, doi. 10.1038/s41598-023-44287-0
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- Article
Recent results from the DANSS experiment.
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- International Journal of Modern Physics A: Particles & Fields; Gravitation; Cosmology; Nuclear Physics, 2024, v. 39, n. 31, p. 1, doi. 10.1142/S0217751X24430103
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New results from the DANSS experiment.
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- International Journal of Modern Physics A: Particles & Fields; Gravitation; Cosmology; Nuclear Physics, 2023, v. 38, n. 18/19, p. 1, doi. 10.1142/S0217751X23410026
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- Article
Optimal controller design for reactor core power stabilization in a pressurized water reactor: Applications of gold rush algorithm.
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- PLoS ONE, 2024, v. 19, n. 1, p. 1, doi. 10.1371/journal.pone.0296987
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- Article
Analysis of the triga mark-II benchmark ieu-comp-therm-003 with monte carlo code openmc.
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- Journal of the Bangladesh Academy of Sciences, 2024, v. 48, n. 2, p. 231, doi. 10.3329/jbas.v48i2.74157
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- Article
Investigation of Underwater Radioactive Objects in Stepovoy Bay (Novaya Zemlya).
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- Oceanology (00014370), 2024, v. 64, n. 6, p. 892, doi. 10.1134/S0001437024700619
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- Article
Creep Properties of 9Cr and 14Cr ODS Tubes Tested by Inner Gas Pressure.
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- Metallurgical & Materials Transactions. Part A, 2021, v. 52, n. 8, p. 3541, doi. 10.1007/s11661-021-06327-0
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- Article
Investigation of Radioisotopes Produced in the Core of a Navy Nuclear Reactor with Low- and High-Enriched Uranium Flues During One Cycle.
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- Energy Sources Part A: Recovery, Utilization & Environmental Effects, 2023, v. 45, n. 1, p. 61, doi. 10.1080/15567036.2022.2164095
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- Article
3D-printed reactor core improves efficiency of solar-fuel production.
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- Chemical Engineering, 2023, v. 130, n. 12, p. 8
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- Article