Works matching DE "BOILING water reactors"
Results: 295
Investigation of surface treatment effects on the environmentally-assisted cracking behaviour of Alloy 182 in boiling water reactor environment.
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- Corrosion Engineering, Science & Technology, 2022, v. 57, n. 5, p. 474, doi. 10.1080/1478422X.2022.2083746
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- Article
Assessment of the platinum deposition behaviour on stainless steel surfaces in a boiling water reactor plant.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, n. 8, p. 578, doi. 10.1080/1478422X.2017.1357959
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- Article
Using tapered specimens to study the effect of hydrogen and surface finish on SCC initiation in Alloy 182 under boiling water reactor conditions.
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- Corrosion Engineering, Science & Technology, 2017, v. 52, n. 8, p. 558, doi. 10.1080/1478422X.2017.1340245
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- Article
Influence of reference electrode distance and hydrogen content on electrochemical potential noise during SCC in high purity, high temperature water.
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- Corrosion Engineering, Science & Technology, 2013, v. 48, n. 3, p. 199, doi. 10.1179/1743278212Y.0000000061
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- Article
Effect of Pt injection rate on corrosion potential and Pt distribution on stainless steel under simulated boiling water reactor conditions.
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- Corrosion Engineering, Science & Technology, 2012, v. 47, n. 7, p. 489, doi. 10.1179/1743278212Y.0000000031
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- Article
GE pins hopes on new nuclear reactor.
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- Power Engineer, 2005, v. 19, n. 3, p. 6
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- Article
ДОСЛІДЖЕННЯ МІЖКРИСТАЛІТНОГО КОРОЗІЙНОГО РОЗТРІСКУВАННЯ ЗВАРНИХ З’ЄДНАНЬ ТРУБОПРОВОДІВ ЧОРНОБИЛЬСЬКОЇ АЕС. МАТЕРІАЛОЗНАВЧИЙ АСПЕКТ.
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- Technical Diagnostics & Nondestructive Testing / Tekhnicheskaya Diagnostika I Nerazrushayushchiy Kontrol, 2024, n. 4, p. 23, doi. 10.37434/tdnk2024.04.04
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- 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.
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- Japanese Journal of Multiphase Flow, 2021, v. 35, n. 1, p. 159
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- Article
沸騰水型原子炉の高温高圧条件における 液膜厚さ計測に向けたケプストラム差分法の適用性検討
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- Japanese Journal of Multiphase Flow, 2020, v. 34, n. 4, p. 520
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- Article
Effect of surface machining on the environmentally-assisted cracking of Alloy 182 and 316L stainless steel in light water reactor environments: results of the collaborative project MEACTOS.
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- Corrosion Reviews, 2023, v. 41, n. 5, p. 545, doi. 10.1515/corrrev-2022-0121
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ABWR.
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- Insight: Non-Destructive Testing & Condition Monitoring, 2016, p. 5
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- Article
The Hollow Promise of Small Modular Nuclear Reactors.
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- CounterPunch, 2022, p. 1
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- Article
The myth of the boiling point.
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- Science Progress, 2008, v. 91, n. 3, p. 219, doi. 10.3184/003685008X360632
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Safety aspect concerning radiolytic gas generation in reactors.
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- Science Progress, 2001, v. 84, n. 1, p. 69, doi. 10.3184/003685001783239087
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- Article
Residence-time distribution of particles in the post of a circulating boiling bed.
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- Journal of Engineering Physics & Thermophysics, 2006, v. 79, n. 3, p. 591, doi. 10.1007/s10891-006-0140-z
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- Article
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2.
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- Journal of Nuclear Science & Technology, 2024, v. 61, n. 11, p. 1453, doi. 10.1080/00223131.2024.2350534
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- Article
N-(1-nitroalkylmethyl)-2(3)-vinyloxyalkylamines.
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- Russian Journal of Organic Chemistry, 2009, v. 45, n. 8, p. 1248, doi. 10.1134/S1070428009080235
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- Article
Analysis of processes in RBMK-1500 fuel assemblies during normal operation cycle.
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- Energetika, 2010, n. 1, p. 8
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- Article
FEMAXI-6 programų paketo taikymas modeliuojant procesus, vykstančius RBMK-1500 šilumą išskiriančiuose elementuose.
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- Energetika, 2009, n. 2, p. 65
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- Article
Framatome in record burn-up.
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- International Power Generation, 2001, v. 24, n. 4, p. 8
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- Article
Modeling a Porous Region for Natural Convection Heat Transfer and Experimental Validation in Slender Cylindrical Geometries.
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- Nuclear Technology, 2016, v. 193, n. 3, p. 375, doi. 10.13182/NT15-56
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- Article
A Core Design Study for a Small Modular Boiling Water Reactor with Long-Life Core.
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- Nuclear Technology, 2016, v. 193, n. 3, p. 364, doi. 10.13182/NT15-58
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- Article
BWR Station Blackout: A RISMC Analysis Using RAVEN and RELAP5-3D.
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- Nuclear Technology, 2016, v. 193, n. 1, p. 161, doi. 10.13182/NT14-142
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- Article
TRADE-OFF STUDIES FOR THE FUEL-SELF-SUSTAINING RBWR-Th CORE.
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- Nuclear Technology, 2015, v. 191, n. 3, p. 282, doi. 10.13182/NT14-106
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- Article
FUEL PERFORMANCE ANALYSIS OF A (ThU)O<sub>2</sub>-FUELED, REDUCED MODERATION BOILING WATER REACTOR.
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- Nuclear Technology, 2015, v. 191, n. 3, p. 268, doi. 10.13182/NT14-104
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- Article
THE MODELING OF ADVANCED BWR FUEL DESIGNS WITH THE NRC FUEL DEPLETION CODES PARCS/PATHS.
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- Nuclear Technology, 2015, v. 190, n. 3, p. 323, doi. 10.13182/NT14-79
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- Article
EVALUATION OF HELICAL-CRUCIFORM FUEL ROD ASSEMBLIES FOR HIGH-POWER-DENSITY LWRs.
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- Nuclear Technology, 2014, v. 188, n. 2, p. 139, doi. 10.13182/NT13-104
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- Article
COMPARISON OF RADIONUCLIDE RELEASES FROM A CONCEPTUAL GEOLOGICAL REPOSITORY FOR RBMK-1500 AND BWR SPENT NUCLEAR FUEL.
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- Nuclear Technology, 2014, v. 185, n. 3, p. 322, doi. 10.13182/NT13-52
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- Article
ON THE USE OF REDUCED-MODERATION LWRS FOR TRANSURANIC ISOTOPE BURNING IN THORIUM FUEL--II: CORE ANALYSIS.
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- Nuclear Technology, 2014, v. 185, n. 2, p. 147, doi. 10.13182/NT13-54
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ON THE USE OF REDUCED-MODERATION LWRs FOR TRANSURANIC ISOTOPE BURNING IN THORIUM FUEL--I: ASSEMBLY ANALYSIS.
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- Nuclear Technology, 2014, v. 185, n. 2, p. 127, doi. 10.13182/NT13-53
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STABILITY ANALYSIS OF BWR-HD: AN OPTIMIZED BOILING WATER REACTOR WITH HIGH POWER DENSITY.
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- Nuclear Technology, 2013, v. 184, n. 3, p. 287, doi. 10.13182/NT13-A24986
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SAFETY ANALYSIS OF BWR-HD: AN OPTIMIZED BOILING WATER REACTOR WITH HIGH POWER DENSITY.
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- Nuclear Technology, 2013, v. 184, n. 3, p. 284, doi. 10.13182/NT13-A24985
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- Article
BWR-HD: AN OPTIMIZED BOILING WATER REACTOR WITH HIGH POWER DENSITY.
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- Nuclear Technology, 2013, v. 184, n. 3, p. 261, doi. 10.13182/NT13-A24984
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- Article
METHOD FOR ANALYZING FISSION GAS RELEASE IN FUEL RODS BASED ON GAMMA-RAY MEASUREMENTS OF SHORT-LIVED FISSION PRODUCTS.
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- Nuclear Technology, 2013, v. 184, n. 1, p. 96, doi. 10.13182/NT13-A19871
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- Article
SIMULATION OF IN-CORE NEUTRON NOISE MEASUREMENTS FOR AXIAL VOID PROFILE RECONSTRUCTION IN BOILING WATER REACTORS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 354, doi. 10.13182/NT13-A19424
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TRANSITION TO CASMO-5M AND SIMULATE-3K FOR STABILITY ANALYSES OF THE SWISS BOILING WATER REACTORS.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 341, doi. 10.13182/NT13-A19423
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- Article
DRYOUT METHODOLOGY WITH NEW STEADY-STATE CRITERION AND MORE-ACCURATE STATISTICAL TREATMENT OF CHANNEL BOW.
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- Nuclear Technology, 2013, v. 183, n. 3, p. 298, doi. 10.13182/NT13-A19419
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SENSITIVITY AND UNCERTAINTY OF OECD BENCHMARK RINGHALS-1 TRACE/PARCS STABILITY PREDICTION.
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- Nuclear Technology, 2012, v. 180, n. 3, p. 383, doi. 10.13182/NT12-A15351
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- Article
VERIFICATION AND VALIDATION OF EVALUATION PROCEDURES FOR LOCAL WALL THINNING DUE TO FLOW-ACCELERATED CORROSION AND LIQUID DROPLET IMPINGEMENT.
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- Nuclear Technology, 2012, v. 178, n. 3, p. 280, doi. 10.13182/NT12-A13594
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COMBINED MICRO AND MACRO PARAMETER PERTURBATION THEORY AND APPLICATION FOR BWR LATTICE DESIGN AND OPTIMIZATION.
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- Nuclear Technology, 2012, v. 177, n. 2, p. 157, doi. 10.13182/NT12-A13363
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BOILING WATER REACTOR STABILITY ANALYSIS BY TRACE/PARCS: MODELING EFFECTS AND CASE STUDY OF TIME VERSUS FREQUENCY DOMAIN APPROACH.
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- Nuclear Technology, 2012, v. 177, n. 1, p. 8, doi. 10.13182/NT12-A13324
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HOMOGENIZATION OF CROSS SECTIONS AND COMPUTATION OF DISCONTINUITY FACTORS FOR A REAL 3-D BWR BOTTOM REFLECTOR FOR COMPARISON WITH LATTICE AND NODAL CODES.
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- Nuclear Technology, 2012, v. 177, n. 1, p. 1, doi. 10.13182/NT12-A13323
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QUALIFICATION OF THE RELAP5/PARCS CODE FOR BWR STABILITY EVENTS PREDICTION.
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- Nuclear Technology, 2011, v. 174, n. 1, p. 51, doi. 10.13182/NT11-A11679
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A LARGE ASSEMBLY WITH SMALL PINS CONCEPT FOR HIGH-POWER-DENSITY BWRs.
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- Nuclear Technology, 2010, v. 171, n. 1, p. 38, doi. 10.13182/NT10-A10771
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SAFETY EVALUATION OF THE UPRATE BWR USING THE LARGE ASSEMBLY WITH SMALL PINS CONCEPT.
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- Nuclear Technology, 2010, v. 171, n. 1, p. 27, doi. 10.13182/NT10-A10770
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STABILITY ANALYSES OF THE UPRATED BWR USING THE LARGE ASSEMBLY WITH SMALL PINS CONCEPT.
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- Nuclear Technology, 2010, v. 171, n. 1, p. 1, doi. 10.13182/NT10-A10768
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AUTOMATIC POWER ASCENSION SEARCH FOR A BOILING WATER REACTOR USING ANT COLONY OPTIMIZATION ALGORITHM.
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- Nuclear Technology, 2010, v. 170, n. 2, p. 281, doi. 10.13182/NT10-A9483
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ANALYSIS OF A COUPLED BLOWDOWN FROM BOTH RPV AND BOP WITH RELAP5-3D/K FOR A LIMITING FWLB OF AN ABWR FOR CONTAINMENT DESIGN.
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- Nuclear Technology, 2010, v. 169, n. 1, p. 50, doi. 10.13182/NT10-A9342
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IMPORTANCE RANKING OF PARAMETERS AFFECTING REACTOR DYNAMICS USING THE TAGUCHI METHOD.
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- Nuclear Technology, 2010, v. 169, n. 1, p. 18, doi. 10.13182/NT10-A9340
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- Article
BENCHMARK OF NATURAL CONVECTION/RADIATION SIMULATIONS WITHIN AN ENCLOSED ARRAY OF HORIZONTAL HEATED RODS.
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- Nuclear Technology, 2009, v. 167, n. 3, p. 384, doi. 10.13182/NT09-A9078
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- Article