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Issues
April 2017
ISSN 2332-8983
EISSN 2332-8975
Guest Editorial
Special Section: Pressurized Heavy Water Reactors Safety
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020301.
doi: https://doi.org/10.1115/1.4035852
Topics:
Design
,
Heavy water reactors
,
Safety
,
Accidents
,
Water
,
Nuclear engineering
,
Thermal hydraulics
Special Section Papers
Pressurized Heavy Water Reactor Technology: Its Relevance Today
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020901.
doi: https://doi.org/10.1115/1.4035856
Topics:
Heavy water reactors
,
Fuels
,
Uranium
Development of Technologies and Safety Systems for Pressurized Heavy Water Reactors in India
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020902.
doi: https://doi.org/10.1115/1.4035435
Topics:
Heavy water reactors
,
Safety
,
Fuels
,
Design
Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications
Thambiayah Nitheanandan, X. Cao, J.-H. Choi, D. Dupleac, D.-H. Kim, H. G. Lele, A. K. Nayak, H. P. Rammohan
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020903.
doi: https://doi.org/10.1115/1.4035726
Topics:
Accidents
,
Heat
,
Vessels
,
Water
,
Heavy water reactors
,
Computers
,
Pressure
,
Fuels
,
Containment
,
Boilers
Analysis of Late Phase Severe Accident Phenomena in CANDU Plant
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020904.
doi: https://doi.org/10.1115/1.4035416
Topics:
Accidents
,
Vessels
,
Water
,
Zirconium
,
Steam
,
Failure
,
Heat transfer coefficients
,
Temperature
Thermomechanical Behavior of Coolant Channel Assembly in Heavy Water Reactor Under Severe Plant Condition
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020905.
doi: https://doi.org/10.1115/1.4035784
Topics:
Contact resistance
,
Coolants
,
Deformation
,
Heat
,
Heavy water reactors
,
Manufacturing
,
Pressure
,
Temperature
,
Thermomechanics
,
Flow (Dynamics)
Combining RAVEN, RELAP5-3D, and PHISICS for Fuel Cycle and Core Design Analysis for New Cladding Criteria
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020906.
doi: https://doi.org/10.1115/1.4035851
Topics:
Accidents
,
Cladding systems (Building)
,
Coolants
,
Cycles
,
Design
,
Flow (Dynamics)
,
Fuels
,
Nuclear fuel cycle
,
Oxidation
,
Safety
Effects of Filtered Containment Venting on Fission Product Releases During CANDU Reactor Severe Accidents
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020907.
doi: https://doi.org/10.1115/1.4035434
Topics:
Accidents
,
Containment
,
Nuclear fission
,
Failure
,
Pressure
,
Vessels
Collapse Criterion for the CANDU 6 Calandria Vault Floor During a Severe Accident
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020908.
doi: https://doi.org/10.1115/1.4035336
Topics:
Accidents
,
Collapse
,
Concretes
,
Finite element model
,
Stress
,
Temperature
,
Thermal expansion
,
Failure
In-Calandria Retention of Corium in PHWR: Experimental Investigation and Remaining Issues
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020909.
doi: https://doi.org/10.1115/1.4035691
Topics:
Accidents
,
Heat
,
Heat transfer
,
Heavy water reactors
,
Vessels
,
Water
,
Temperature
,
Cooling
Progression of Severe Accidents, Containment Performance, and Estimates of Releases of Radionuclides-Level-2 Probabilistic Safety Assessment IPHWR
ASME J of Nuclear Rad Sci. April 2017, 3(2): 020910.
doi: https://doi.org/10.1115/1.4035783
Topics:
Accidents
,
Containment
,
Failure
,
Safety
,
Probabilistic safety assessment
,
Accident management
,
Radioisotopes
Research Papers
Statistical Modeling of Stratified Two-Phase Flow
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021001.
doi: https://doi.org/10.1115/1.4035564
Topics:
Flow (Dynamics)
,
Turbulence
,
Waves
,
Kinetic energy
,
Spectra (Spectroscopy)
,
Two-phase flow
Experimental Study of Aqueous Chemical Trisodium Phosphate-Buffered Environment Under Post-LOCA Conditions With Head Loss Measurements
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021002.
doi: https://doi.org/10.1115/1.4034572
Topics:
Aluminum
,
Corrosion
,
Epoxy adhesives
,
Epoxy resins
,
Fibers
,
Flow (Dynamics)
,
Metals
,
Temperature
,
Testing
,
Water
A Feasibility Study of Noncontact Ultrasonic Sensor for Nuclear Power Plant Inspection
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021003.
doi: https://doi.org/10.1115/1.4035466
Validation of Constant Load C-Ring Apex Stresses for Stress Corrosion Cracking Testing in Supercritical Water
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021004.
doi: https://doi.org/10.1115/1.4034567
Topics:
Deflection
,
Springs
,
Stress
,
Stress corrosion cracking
,
Testing
,
Temperature
,
Thermal expansion
,
Water
,
Metals
Development of SNTA Code System for SCWR Core Steady-State Analysis
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021005.
doi: https://doi.org/10.1115/1.4035334
Adhesion of Oxides Grown in Supercritical Water on Selected Austenitic and Ferritic/Martensitic Alloys
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021006.
doi: https://doi.org/10.1115/1.4035331
Topics:
Alloys
,
Delamination
,
Adhesion
,
Descaling (Metals)
A Review of the Turbine Cooling Fraction for Very High Turbine Entry Temperature Helium Gas Turbine Cycles for Generation IV Reactor Power Plants
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021007.
doi: https://doi.org/10.1115/1.4035332
Topics:
Cooling
,
Cycles
,
Temperature
,
Turbines
,
Flow (Dynamics)
,
Pressure
,
Blades
Results of Air Barbotage Experiments Simulating Two-Phase Flow in a CANDU End Shield During In-Vessel Retention
ASME J of Nuclear Rad Sci. April 2017, 3(2): 021008.
doi: https://doi.org/10.1115/1.4035566
Topics:
Boiling
,
Cavities
,
Flow visualization
,
Heat
,
Heat flux
,
Vessels
,
Water
,
Accidents
,
Air flow
,
Porous materials
Technical Brief
Current Severe Accident Research and Development Topics for Wolsong PHWR Safety in Korea
ASME J of Nuclear Rad Sci. April 2017, 3(2): 024501.
doi: https://doi.org/10.1115/1.4035690
Topics:
Accidents
,
Containment
,
Heavy water reactors
,
Overpressure protection
,
Safety
,
Heat
,
Design
,
Computers
Thermal-Hydraulic Model and Program Development for Helium-Cooled Accelerator-Driven System
ASME J of Nuclear Rad Sci. April 2017, 3(2): 024502.
doi: https://doi.org/10.1115/1.4035333
Topics:
Heat
,
Heat transfer
,
Helium
,
Transients (Dynamics)
,
Cooling systems
,
Mathematics
,
Fluids
Book Review
Handbook of Generation-IV Nuclear Reactors
ASME J of Nuclear Rad Sci. April 2017, 3(2): 026501.
doi: https://doi.org/10.1115/1.4035327
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