Works matching IS 16876075 AND DT 2015 AND VI 2015
Results: 48
An Innovative Passive Residual Heat Removal System of an Open-Pool Type Research Reactor with Pump Flywheel and Gravity Core Cooling Tank.
- Published in:
- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/150373
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- Article
Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment with ERANOS and RELAP.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/832721
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- Article
Temperature Response of the HTR-10 during the Power Ascension Test.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/302648
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- Article
Monte Carlo Alpha Iteration Algorithm for a Subcritical System Analysis.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/859242
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- Article
Advanced Integral Type Reactors: Passive Safety Design and Experiment.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/491715
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- Article
Input Calibration and Validation of RELAP5 Against CIRCUS-IV Single Channel Tests on Natural Circulation Two-Phase Flow Instability.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/130741
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- Article
Study on the Effects of Liquid Thermal Media on the Irradiation Capsule of High-Temperature Materials.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/723081
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- Article
Integrated Deterministic and Probabilistic Safety Analysis for Safety Assessment of Nuclear Power Plants.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/136940
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- Article
Probabilistic Dynamics for Integrated Analysis of Accident Sequences considering Uncertain Events.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/892502
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- Article
Demonstration of Emulator-Based Bayesian Calibration of Safety Analysis Codes: Theory and Formulation.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/839249
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- Article
Safety Assessment of Nuclear Power Plants for Liquefaction Consequences.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/727291
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- Article
Risk-Based Clustering for Near Misses Identification in Integrated Deterministic and Probabilistic Safety Analysis.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/693891
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- Article
A Flooding Induced Station Blackout Analysis for a Pressurized Water Reactor Using the RISMC Toolkit.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/308163
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- Publication type:
- Article
Scenario Grouping and Classification Methodology for Postprocessing of Data Generated by Integrated Deterministic-Probabilistic Safety Analysis.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/278638
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- Publication type:
- Article
Improved Modelling and Assessment of the Performance of Firefighting Means in the Frame of a Fire PSA.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/238723
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- Publication type:
- Article
An Enhanced Preventive Maintenance Optimization Model Based on a Three-Stage Failure Process.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/193075
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- Article
Delayed Station Blackout Event and Nuclear Safety.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/192601
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- Article
Methods and Models for the Coupled Neutronics and Thermal-Hydraulics Analysis of the CROCUS Reactor at EFPL.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/237646
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- Article
Properties of Neutron Noise Induced by Localized Perturbations in an SFR.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/140979
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- Publication type:
- Article
Full Scope Modeling and Analysis on the Secondary Circuit of Chinese Large-Capacity Advanced PWR Based on RELAP5 Code.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/913274
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- Publication type:
- Article
Analysis of Wetting Characteristics on Microstructured Hydrophobic Surfaces for the Passive Containment Cooling System.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/652731
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- Article
Multilayered Pipe Cutting Test for Remote Handling Maintenance.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/920183
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- Article
Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/198654
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- Article
Transuranics Transmutation Using Neutrons Spectrum from Spallation Reactions.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/104739
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- Publication type:
- Article
CANDU Safety R&D Status, Challenges, and Prospects in Canada.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/143767
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- Publication type:
- Article
Void Reactivity Coefficient Analysis during Void Fraction Changes in Innovative BWR Assemblies.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/757201
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- Article
The Effects of the Treatment of the Periodic Boundary Condition in TRIAINA Codes with a Pressure Tube Creep Problem.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/571547
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- Article
Safety Enhancements for PHWRs Based on Macroscopic Losses of the Fukushima Accident.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/520756
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- Article
Uncertainty Analysis of the Potential Hazard of MCCI during Severe Accidents for the CANDU6 Plant.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/462941
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- Article
Measurement of Velocity and Temperature Profiles in the 1/40 Scaled-Down CANDU-6 Moderator Tank.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/439863
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- Article
Monte Carlo Few-Group Constant Generation for CANDU 6 Core Analysis.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/284642
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- Article
CHF Enhancement of Advanced 37-Element Fuel Bundles.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/243867
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- Article
Alpha Stable Distribution Based Morphological Filter for Bearing and Gear Fault Diagnosis in Nuclear Power Plant.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/460131
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- Article
An Improved Shuffled Frog Leaping Algorithm for Assembly Sequence Planning of Remote Handling Maintenance in Radioactive Environment.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/516470
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- Article
On Some Fundamental Peculiarities of the Traveling Wave Reactor.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/703069
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- Publication type:
- Article
Influence of the Saturation Ratio on Concrete Behavior under Triaxial Compressive Loading.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/976387
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- Article
Integrated Cost and Schedule Control Systems for Nuclear Power Plant Construction: Leveraging Strategic Advantages to Owners and EPC Firms.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/190925
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- Article
HTR-Based Power Plants’ Performance Analysis Applied on Conventional Combined Cycles.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/716572
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- Article
Simulation of a TRIGA Reactor Core Blockage Using RELAP5 Code.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/354163
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- Article
Safety Assessment of Low-Contaminated Equipment Dismantling at Nuclear Power Plants.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/650810
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- Publication type:
- Article
AP1000 Shield Building Dynamic Response for Different Water Levels of PCCWST Subjected to Seismic Loading considering FSI.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/840507
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- Publication type:
- Article
Development of the Noncontact Temperature Sensor Using the Infrared Optical Fiber Coated with Antifog Solution.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/718592
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- Publication type:
- Article
Scientific and Engineering Literature Mini Review of Molten Salt Oxidation for Radioactive Waste Treatment and Organic Compound Gasification as well as Spent Salt Treatment.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/407842
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- Publication type:
- Article
Study on the Use of Hydride Fuel in High-Performance Light Water Reactor Concept.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/965274
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- Publication type:
- Article
Single Phase Natural Circulation Behaviors of the Integral Type Marine Reactor Simulator under Rolling Motion Condition.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/815603
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- Publication type:
- Article
Research and Evaluation for Passive Safety System in Low Pressure Reactor.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/179235
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- Publication type:
- Article
INPRO Activities on Development of Advanced Tools to Support Judgment Aggregation for Comparative Evaluation of Nuclear Energy Systems.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/910162
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- Publication type:
- Article
SIMMER-III Analyses of Local Fuel-Coolant Interactions in a Simulated Molten Fuel Pool: Effect of Coolant Quantity.
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- Science & Technology of Nuclear Installations, 2015, v. 2015, p. 1, doi. 10.1155/2015/964327
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- Publication type:
- Article