Works matching DE "NUCLEAR reactor safety measures"
Results: 186
Nuclear safety lies in greater transparency.
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- Nature, 2013, v. 494, n. 7438, p. 403, doi. 10.1038/494403a
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- Article
Tsallis Entropy Segmentation and Shape Feature-based Classification of Defects in the Simulated Magnetic Flux Leakage Images of Steam Generator Tubes.
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- International Journal of Pattern Recognition & Artificial Intelligence, 2020, v. 34, n. 1, p. N.PAG, doi. 10.1142/S0218001420540026
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- Article
Thermal and neutron-physical features of the nuclear reactor for a power pulsation plant for space applications.
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- Journal of Engineering Physics & Thermophysics, 2012, v. 85, n. 3, p. 700, doi. 10.1007/s10891-012-0704-z
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- Article
Nuclear safety convention comes into force in October.
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- Journal of Medicine & Philosophy, 1996, p. 3
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- Article
A study on the fracture pattern change of high-burnup fuel cladding failed by pellet-cladding mechanical interaction failure under reactivity-initiated accident conditions.
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- Journal of Nuclear Science & Technology, 2024, v. 61, n. 9, p. 1265, doi. 10.1080/00223131.2024.2313553
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- Article
Thoughts on the Book Nuclear Reactor Safety.
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- 2014
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- Publication type:
- Book Review
Selin on safety.
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- Bulletin of the Atomic Scientists, 1994, v. 50, n. 6, p. 13, doi. 10.1080/00963402.1994.11456568
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- Article
In search of a safe reactor.
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- Bulletin of the Atomic Scientists, 1986, v. 42, n. 8, p. 3, doi. 10.1080/00963402.1986.11459413
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- Article
The Impact of Energy.
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- 1975
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- Publication type:
- Letter
Cart Before the Horse.
- Published in:
- 1975
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- Publication type:
- Letter
The Wrong Point.
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- 1975
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- Publication type:
- Letter
Scientific Elite.
- Published in:
- 1975
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- Publication type:
- Letter
The author replies.
- Published in:
- 1975
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- Publication type:
- Letter
Make Them Better.
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- 1975
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- Publication type:
- Letter
Nuclear Reactor Safety.
- Published in:
- Bulletin of the Atomic Scientists, 1974, v. 30, n. 8, p. 5, doi. 10.1080/00963402.1974.11458148
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- Publication type:
- Article
RBMK-1500 reaktoriaus neutroninės-fizikinės charakteristikos vykdant aktyviosios zonos modifikacijas 2004-2009 m.
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- Energetika, 2011, v. 57, n. 2, p. 71, doi. 10.6001/energetika.v57i2.2062
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- Publication type:
- Article
Branduolinių reaktoriu saugos sistemų programines įrangos patikimumas: vertinimo metodai ir problemos.
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- Energetika, 2006, n. 4, p. 45
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- Publication type:
- Article
Environmental and Safety Concerns for Nuclear Power Generation in Ghana.
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- Environmental Research, Engineering & Management / Aplinkos Tyrimai, Inžinerija ir Vadyba, 2011, v. 55, n. 1, p. 49
- Publication type:
- Article
Safety upgrades.
- Published in:
- International Power Generation, 1997, v. 20, n. 5, p. 65
- Publication type:
- Article
AN ADVANCED ONE-DIMENSIONAL FINITE ELEMENT MODEL FOR INCOMPRESSIBLE THERMALLY EXPANDABLE FLOW.
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- Nuclear Technology, 2015, v. 190, n. 3, p. 313, doi. 10.13182/NT14-78
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- Publication type:
- Article
MODIFICATION OF SCWR ASSEMBLY DESIGNS WITH COUPLED MCNP5/SCA METHODS TO PROMOTE SAFER OPERATION.
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- Nuclear Technology, 2015, v. 190, n. 3, p. 292, doi. 10.13182/NT14-74
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- Publication type:
- Article
EXPERIMENTAL INVESTIGATION INTO THE EFFECT OF THE PASSIVE CONDENSATION COOLING TANK WATER LEVEL IN THE THERMAL PERFORMANCE OF THE PASSIVE AUXILIARY FEEDWATER SYSTEM.
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- Nuclear Technology, 2013, v. 181, n. 3, p. 479, doi. 10.13182/NT181-479
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- Publication type:
- Article
KOREAN DEVELOPMENT OF ADVANCED THERMAL-HYDRAULIC CODES FOR WATER REACTORS AND HTGRs: SPACE AND GAMMA.
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- Nuclear Technology, 2013, v. 181, n. 1, p. 24, doi. 10.13182/NT13-A15754
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- Publication type:
- Article
THERMAL HYDRAULICS OF SODIUM-COOLED FAST REACTORS: KEY DESIGN AND SAFETY ISSUES AND HIGHLIGHTS.
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- Nuclear Technology, 2013, v. 181, n. 1, p. 11, doi. 10.13182/NT13-A15753
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- Publication type:
- Article
ANALYSIS OF BR2 LOSS-OF-FLOW TESTS C AND F.
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- Nuclear Technology, 2012, v. 179, n. 3, p. 382, doi. 10.13182/NT12-A14170
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- Publication type:
- Article
EVALUATION OF JSFR KEY TECHNOLOGIES.
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- Nuclear Technology, 2012, v. 179, n. 3, p. 360, doi. 10.13182/NT179-360
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- Publication type:
- Article
REACTOR LOOSE PART DAMAGE ASSESSMENTS ON STEAM GENERATOR TUBE SHEETS.
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- Nuclear Technology, 2012, v. 179, n. 3, p. 339, doi. 10.13182/NT12-A14167
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- Publication type:
- Article
DYNAMIC SAFETY ANALYSIS OF THE SABR SUBCRITICAL TRANSMUTATION REACTOR CONCEPT.
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- Nuclear Technology, 2010, v. 171, n. 2, p. 123, doi. 10.13182/NT10-A10777
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- Publication type:
- Article
FORMAL CONSIDERATIONS IN ESTABLISHING RISK-CONSISTENT ACCEPTANCE CRITERIA FOR REACTOR SAFETY.
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- Nuclear Technology, 2010, v. 170, n. 3, p. 383, doi. 10.13182/NT10-A10325
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- Publication type:
- Article
ACOUSTIC LEAK DETECTION TECHNOLOGY FOR WATER/STEAM SMALL LEAKS AND MICROLEAKS INTO SODIUM TO PROTECT AN SFR STEAM GENERATOR.
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- Nuclear Technology, 2010, v. 170, n. 2, p. 360, doi. 10.13182/NT10-A9489
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- Publication type:
- Article
VALIDATION OF THE DALTON-THERMIX CODE SYSTEM WITH TRANSIENT ANALYSES OF THE HTR-10 AND APPLICATION TO THE PBMR.
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- Nuclear Technology, 2010, v. 170, n. 2, p. 306, doi. 10.13182/NT10-A9485
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- Publication type:
- Article
NEW DESIGN OPTIONS FREE FROM A POTENTIAL SODIUM FREEZING ISSUE FOR A PASSIVE DHR SYSTEM OF KALIMER.
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- Nuclear Technology, 2010, v. 170, n. 2, p. 290, doi. 10.13182/NT10-A9484
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- Publication type:
- Article
Gain-phase margins-based delay-dependent stability analysis of pitch control system of large wind turbines.
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- Transactions of the Institute of Measurement & Control, 2019, v. 41, n. 13, p. 3626, doi. 10.1177/0142331219834605
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- Publication type:
- Article
A Compartmented Microfluidic Reactor for Protein Modification Via Solid-phase Reactions — Semi-automated Examination of Two PEGylation Routes.
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- Biotechnology & Bioprocess Engineering, 2019, v. 24, n. 2, p. 382, doi. 10.1007/s12257-017-0322-x
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- Publication type:
- Article
Influence of Two-Phase Crossflow for Void Prediction in Bundles Using Thermal-Hydraulic System Codes †.
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- Energies (19961073), 2020, v. 13, n. 14, p. 3686, doi. 10.3390/en13143686
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- Publication type:
- Article
Profitability Analysis and Capital Cost Estimation of a Thermochemical Energy Storage System Utilizing Fluidized Bed Reactors and the Reaction System MgO/Mg(OH)2.
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- Energies (19961073), 2019, v. 12, n. 24, p. 4788, doi. 10.3390/en12244788
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- Article
Model-Free Coordinated Control for MHTGR-Based Nuclear Steam Supply Systems.
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- Energies (19961073), 2016, v. 9, n. 1, p. 37, doi. 10.3390/en9010037
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- Publication type:
- Article
Experimental and Numerical Study on the Characteristics of the Thermal Design of a Large-Area Hot Plate for Nanoimprint Equipment.
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- Sustainability (2071-1050), 2019, v. 11, n. 17, p. 4795, doi. 10.3390/su11174795
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- Article
Safe use of atomic (Nuclear) power (Nuclear Safety).
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- Physics of Atomic Nuclei, 2013, v. 76, n. 13, p. 1621, doi. 10.1134/S1063778813130103
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- Publication type:
- Article
Full-scale mathematical model for describing the temperature conditions of a reactor of the RBMK type in the case of an accident with complete deenergization.
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- Physics of Atomic Nuclei, 2013, v. 76, n. 13, p. 1595, doi. 10.1134/S106377881313005X
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- Publication type:
- Article
Statistical verification of neutron-physics programs for calculations in support of nuclear safety.
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- Physics of Atomic Nuclei, 2012, v. 75, n. 13, p. 1570, doi. 10.1134/S106377881213008X
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- Publication type:
- Article
Probabilistic Safety Analysis of Nuclear Installations of Different Types and Classes.
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- Atomic Energy, 2021, v. 129, n. 1, p. 46, doi. 10.1007/s10512-021-00710-1
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- Publication type:
- Article
Concept Selection and Neutronic Characteristics of Nuclear Icebreaker Cores.
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- Atomic Energy, 2019, v. 126, n. 1, p. 21, doi. 10.1007/s10512-019-00508-2
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- Publication type:
- Article
Level-3 Probabilistic Safety Analysis VAB-3 as an NPP Safety Enhancement Stage.
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- Atomic Energy, 2018, v. 123, n. 6, p. 418, doi. 10.1007/s10512-018-0362-0
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- Publication type:
- Article
Experimental Validation of the Earthquake Resistance of a Full-Scale Model of RBMK-1000 Graphite Stack with Post-Repair Characteristics.
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- Atomic Energy, 2018, v. 123, n. 5, p. 355, doi. 10.1007/s10512-018-0352-2
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- Publication type:
- Article
Numerical Study of the Dynamic Strength of RBMK-1000 Stack with Fuel Channel Rupture.
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- Atomic Energy, 2018, v. 123, n. 5, p. 349, doi. 10.1007/s10512-018-0351-3
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- Publication type:
- Article
Serviceability of Phase-1 RBMK-1000 FA After Service-Life Characteristics Restoration.
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- Atomic Energy, 2018, v. 123, n. 5, p. 358, doi. 10.1007/s10512-018-0353-1
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- Publication type:
- Article
Economic Aspects of RBMK Service Life Characteristics Restoration.
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- Atomic Energy, 2018, v. 123, n. 5, p. 345, doi. 10.1007/s10512-018-0350-4
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- Publication type:
- Article
Numerical Modeling of RBMK-1000 Graphite Stack Distortion.
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- Atomic Energy, 2018, v. 123, n. 5, p. 339, doi. 10.1007/s10512-018-0349-x
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- Publication type:
- Article
RBMK Graphite Serviceability at the Final Stage of Operation.
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- Atomic Energy, 2018, v. 123, n. 5, p. 332, doi. 10.1007/s10512-018-0348-y
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- Publication type:
- Article