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Journal Articles

Adjuster Absorber Rods Return to Service at PLNGS

J. Krishnamoorthy, D. Deveaux, D. Mullin, E. C. Usalp, L. Sun, J. Sharpe, D. Rouben
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2025, 11(3): 034503.
Paper No: NERS-24-1056
https://doi.org/10.1115/1.4067925
Published Online: March 18, 2025
View Article titled, Adjuster Absorber Rods Return to Service at PLNGS
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Topics: Design, Rods, Shapes, Safety, Fuels
Journal Articles

Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code

E. B. Mweze, J. L. Muswema, G. B. Ekoko, D. G. Kom'bele
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031501.
Paper No: NERS-24-1090
https://doi.org/10.1115/1.4067996
Published Online: March 18, 2025
View Article titled, Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code
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Topics: Neutrons, Nuclear reactors, Rods, Safety, Transients (Dynamics), Model validation, Errors, Neutron flux, Probability, Testing
Image
Cross-section view of TRICO II core, ( x , y ) coordinates

Cross-section view of TRICO II core, ( x , y ) coordinates

in Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code > Journal of Nuclear Engineering and Radiation Science
Published Online: March 18, 2025
Fig. 1 Cross-section view of TRICO II core, ( x , y ) coordinates More about this image found in Cross-section view of TRICO II core, ( x , y ) coordinates
Image
Side view of the TRICO II core, ( y , z ) coordinates

Side view of the TRICO II core, ( y , z ) coordinates

in Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code > Journal of Nuclear Engineering and Radiation Science
Published Online: March 18, 2025
Fig. 2 Side view of the TRICO II core, ( y , z ) coordinates More about this image found in Side view of the TRICO II core, ( y , z ) coordinates
Image
Reactor startup and shutdown techniques

Reactor startup and shutdown techniques

in Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code > Journal of Nuclear Engineering and Radiation Science
Published Online: March 18, 2025
Fig. 3 Reactor startup and shutdown techniques More about this image found in Reactor startup and shutdown techniques
Image
Methodology flowchart used for calculations with OpenMC

Methodology flowchart used for calculations with OpenMC

in Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code > Journal of Nuclear Engineering and Radiation Science
Published Online: March 18, 2025
Fig. 4 Methodology flowchart used for calculations with OpenMC More about this image found in Methodology flowchart used for calculations with OpenMC
Image
Model validation of experimental versus calculated results by OpenMC

Model validation of experimental versus calculated results by OpenMC

in Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code > Journal of Nuclear Engineering and Radiation Science
Published Online: March 18, 2025
Fig. 5 Model validation of experimental versus calculated results by OpenMC More about this image found in Model validation of experimental versus calculated results by OpenMC
Image
Postulated startup operations of TRICO II postulated events

Postulated startup operations of TRICO II postulated events

in Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code > Journal of Nuclear Engineering and Radiation Science
Published Online: March 18, 2025
Fig. 6 Postulated startup operations of TRICO II postulated events More about this image found in Postulated startup operations of TRICO II postulated events
Image
Projection of shutdown operations of TRICO II postulated events

Projection of shutdown operations of TRICO II postulated events

in Study of TRICO II Reactor Startup and Shutdown Operations Using the OpenMC Calculation Code > Journal of Nuclear Engineering and Radiation Science
Published Online: March 18, 2025
Fig. 7 Projection of shutdown operations of TRICO II postulated events More about this image found in Projection of shutdown operations of TRICO II postulated events
Journal Articles

Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Accepted Manuscript
Zhenyu Wang, Xian Zhang, Shichang Liu, Rui Che, Yixue Chen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1095
https://doi.org/10.1115/1.4068167
Published Online: March 13, 2025
View Article titled, Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC
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Topics: Fusion reactors, Radiation (Physics), Algorithms, Resolution (Optics), Accuracy and precision, Computational methods, Geometry, Nuclear design, Particulate matter, Safety
Journal Articles

Kinetic Study of Magnetite Precipitation using a High-Temperature Flow-Through Loop: Experimental Apparatus and Testing Procedure

Accepted Manuscript
Vichaiyut Oancherd, Sarita Weerakul, Camilla Drost, Olga Palazhchenko, Chutima Kongvarhodom
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1107
https://doi.org/10.1115/1.4068168
Published Online: March 13, 2025
View Article titled, Kinetic Study of Magnetite Precipitation using a High-Temperature Flow-Through Loop: Experimental Apparatus and Testing Procedure
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Topics: Flow (Dynamics), High temperature, Magnetite, Precipitation, Testing, Boilers, Temperature, Construction, Coolants, Corrosion
Journal Articles

Mechanical Properties and Radon Gas Emanation Analysis of Composite Bricks Reinforced with Cellulose Nanofibrils and Graphene Oxide

Accepted Manuscript
Nur Atiqah Syahirah Shari, Mohammad Khairul Azhar Abdul Razab, An'amt Mohamed Noor, Mohd Zahri Abdul Aziz, Nor Hakimin Abdullah
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1102
https://doi.org/10.1115/1.4068121
Published Online: March 7, 2025
View Article titled, Mechanical Properties and Radon Gas Emanation Analysis of Composite Bricks Reinforced with Cellulose Nanofibrils and Graphene Oxide
Open the PDF for Mechanical Properties and Radon Gas Emanation Analysis of Composite Bricks Reinforced with Cellulose Nanofibrils and Graphene Oxide in another window
Topics: Bricks, Cellulose, Composite materials, Graphene, Mechanical properties, Bagasse, Compression, Compressive strength, Concretes, Electron field emission
Journal Articles

Reviewer's Recognition

Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Editorial
ASME J of Nuclear Rad Sci. April 2025, 11(2): 020201.
Paper No: NERS-25-1009
https://doi.org/10.1115/1.4067946
Published Online: March 4, 2025
View Article titled, Reviewer's Recognition
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Journal Articles

Radiological Diversification in Indoor Radon and Thoron Levels in Correlations With Various Factors in Residential Dwellings

Sudhir Mittal
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 032002.
Paper No: NERS-24-1096
https://doi.org/10.1115/1.4067685
Published Online: February 26, 2025
View Article titled, Radiological Diversification in Indoor Radon and Thoron Levels in Correlations With Various Factors in Residential Dwellings
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Topics: Building materials, Cancer, Lung, Risk, Ventilation
Journal Articles

A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors

Jinlei Zhao, Lixia He, Haocheng Zhao, Yuqi Zhang, Wentao Li
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031002.
Paper No: NERS-24-1087
https://doi.org/10.1115/1.4067824
Published Online: February 26, 2025
View Article titled, A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors
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Topics: Errors, Fast neutron reactors, Fuels, Liquid metal fast breeder reactors, Neutrons, Regression models, Spent nuclear fuels, Uranium, Cooling, Simulation
Journal Articles

Resolving of Transportation Issue With High Activity Positron Emission Tomography Radiotracer Source to Long Distance Medical Imaging Centers

Arup Kumar Hudait, Sumita Chattopadhyay, Subrata Bera
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031003.
Paper No: NERS-24-1099
https://doi.org/10.1115/1.4067877
Published Online: February 26, 2025
View Article titled, Resolving of Transportation Issue With High Activity Positron Emission Tomography Radiotracer Source to Long Distance Medical Imaging Centers
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Topics: Biomedical imaging, Containers, Emissions, Positrons, Radioactive tracers, Transportation systems, Tungsten, Tungsten alloys, Radiation (Physics), Imaging
Image
Trends in the mass of total Pu in relation to BU, IE, and CT

Trends in the mass of total Pu in relation to BU, IE, and CT

in A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors > Journal of Nuclear Engineering and Radiation Science
Published Online: February 26, 2025
Fig. 1 Trends in the mass of total Pu in relation to BU, IE, and CT More about this image found in Trends in the mass of total Pu in relation to BU, IE, and CT
Image
Curve of BU versus the content of total Pu

Curve of BU versus the content of total Pu

in A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors > Journal of Nuclear Engineering and Radiation Science
Published Online: February 26, 2025
Fig. 2 Curve of BU versus the content of total Pu More about this image found in Curve of BU versus the content of total Pu
Image
Curve of IE versus the content of total Pu

Curve of IE versus the content of total Pu

in A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors > Journal of Nuclear Engineering and Radiation Science
Published Online: February 26, 2025
Fig. 3 Curve of IE versus the content of total Pu More about this image found in Curve of IE versus the content of total Pu
Image
Curve of 244 Cm versus the content of total Pu

Curve of 244 Cm versus the content of total Pu

in A Mathematical Model Design for Pu Content Analyzed by 244 Cm in Spent Fuel of Fast Reactors > Journal of Nuclear Engineering and Radiation Science
Published Online: February 26, 2025
Fig. 4 Curve of 244 Cm versus the content of total Pu More about this image found in Curve of 244 Cm versus the content of total Pu