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Journal Articles

Assessment of Natural Terrestrial Radionuclides and their Radiological Effects on Human Health in Soil Samples of Aravalli Hill and Mining Areas of Northern Rajasthan

Available to Purchase
Accepted Manuscript
Sudhir Mittal, Rohit Mehra, Karan Singh Gill
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-25-1006
https://doi.org/10.1115/1.4068724
Published Online: May 17, 2025
View Articletitled, Assessment of Natural Terrestrial Radionuclides and their Radiological Effects on Human Health in Soil Samples of Aravalli Hill and Mining Areas of Northern Rajasthan
Open the PDF for Assessment of Natural Terrestrial Radionuclides and their Radiological Effects on Human Health in Soil Samples of Aravalli Hill and Mining Areas of Northern Rajasthan in another window
Topics: Mining, Radioisotopes, Soil
Journal Articles

Decay Heat Uncertainty Analysis for VVER Spent Nuclear Fuel

Open Access
Accepted Manuscript
Martin Lovecky, Jiri Zavorka, Tomas Korinek, Radek Skoda
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1072
https://doi.org/10.1115/1.4068690
Published Online: May 15, 2025
View Articletitled, Decay Heat Uncertainty Analysis for VVER Spent Nuclear Fuel
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Topics: Heat, Spent nuclear fuels, Uncertainty analysis
Journal Articles

High-Performance Manufacturing of Canned Main Coolant Pump - Part I: Synergistical Design and Processing Optimization

Available to Purchase
Accepted Manuscript
M.K. Lei, X.P. Zhu, Bao Zhu, Yupeng Li, L. Lin, L.W. Zhang, W.G. Wang, M.Q. Li, Dongjiang Wu, D.M. Guo
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-24-1097
https://doi.org/10.1115/1.4068691
Published Online: May 15, 2025
View Articletitled, High-Performance Manufacturing of Canned Main Coolant Pump - Part I: Synergistical Design and Processing Optimization
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Topics: Coolants, Design, Manufacturing, Optimization, Pumps
Journal Articles

Research on the Impact of Cosmic Ray Induced Neutron Background Based on Nuclear Safeguards Equipment

Available to Purchase
Accepted Manuscript
Lei Bai, Hao-cheng Zhao, Lixia He, He-Wei Dong, Jie-Wen Shao
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci.
Paper No: NERS-25-1012
https://doi.org/10.1115/1.4068654
Published Online: May 12, 2025
View Articletitled, Research on the Impact of Cosmic Ray Induced Neutron Background Based on Nuclear Safeguards Equipment
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Topics: Cosmic rays, Neutrons, Iron, Aluminum, Muons, Accuracy and precision, Atomic number, Geometry, Monte Carlo methods
Journal Articles

Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor

Open Access
A. Nava Dominguez, Xianmin Huang, Michel Gaudet, Kittima Khumsa-Ang, Alberto D'Ansi Mendoza España, Jimmy Chow, Danila Roubtsov, Hygreeva Namburi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. July 2025, 11(3): 031301.
Paper No: NERS-24-1027
https://doi.org/10.1115/1.4068326
Published Online: May 8, 2025
View Articletitled, Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor
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Topics: Cladding systems (Building), Coolants, Design, Fuels, Loss of coolant accidents, Safety, Temperature, Water, Flow (Dynamics), Small modular reactors
Image
Relative total moisture content of rejected steam for temperatures from 400 °C to 650 °C

Relative total moisture content of rejected steam for temperatures from 400...

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 1 Relative total moisture content of rejected steam for temperatures from 400 °C to 650 °C More about this image found in Relative total moisture content of rejected steam for temperatures from 400...
Image
Specific enthalpy of water as a function of pressure, presented as a series of isotherms

Specific enthalpy of water as a function of pressure, presented as a series...

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 2 Specific enthalpy of water as a function of pressure, presented as a series of isotherms More about this image found in Specific enthalpy of water as a function of pressure, presented as a series...
Image
Cross-section view of the SCW-SMR fuel assembly

Cross-section view of the SCW-SMR fuel assembly

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 3 Cross-section view of the SCW-SMR fuel assembly More about this image found in Cross-section view of the SCW-SMR fuel assembly
Image
Radial zone division for full-core burnup calculation

Radial zone division for full-core burnup calculation

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 4 Radial zone division for full-core burnup calculation More about this image found in Radial zone division for full-core burnup calculation
Image
Axial power distributions for different enrichment profiles: maximum enrichment 13% (at bottom segment) with decrement of 0.1%, 0.25%, 0.5%, and 1.0%, versus flat 5% enrichment

Axial power distributions for different enrichment profiles: maximum enrich...

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 5 Axial power distributions for different enrichment profiles: maximum enrichment 13% (at bottom segment) with decrement of 0.1%, 0.25%, 0.5%, and 1.0%, versus flat 5% enrichment More about this image found in Axial power distributions for different enrichment profiles: maximum enrich...
Image
Cross- section views of the Canadian SCWR and SCW-SMR fuel assemblies

Cross- section views of the Canadian SCWR and SCW-SMR fuel assemblies

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 6 Cross- section views of the Canadian SCWR and SCW-SMR fuel assemblies More about this image found in Cross- section views of the Canadian SCWR and SCW-SMR fuel assemblies
Image
Cross-sectional view of the 64-element fuel bundle [15] (not to scale)

Cross-sectional view of the 64-element fuel bundle [ 15 ] (not to scale)

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 7 Cross-sectional view of the 64-element fuel bundle [ 15 ] (not to scale) More about this image found in Cross-sectional view of the 64-element fuel bundle [ 15 ] (not to scale)
Image
Heat transfer characteristics of the Canadian SCW-SMR fuel bundle

Heat transfer characteristics of the Canadian SCW-SMR fuel bundle

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 8 Heat transfer characteristics of the Canadian SCW-SMR fuel bundle More about this image found in Heat transfer characteristics of the Canadian SCW-SMR fuel bundle
Image
Subchannel discretization of the 64-element fuel bundle (only the first quadrant is shown)

Subchannel discretization of the 64-element fuel bundle (only the first qua...

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 9 Subchannel discretization of the 64-element fuel bundle (only the first quadrant is shown) More about this image found in Subchannel discretization of the 64-element fuel bundle (only the first qua...
Image
Assessment of corrosion resistance (in units of mg/dm2/d) of the candidate fuel cladding materials for SCW-SMR application carried out in CNL B350 SCW autoclave facility

Assessment of corrosion resistance (in units of mg/dm 2 /d) of the candidat...

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 10 Assessment of corrosion resistance (in units of mg/dm 2 /d) of the candidate fuel cladding materials for SCW-SMR application carried out in CNL B350 SCW autoclave facility More about this image found in Assessment of corrosion resistance (in units of mg/dm 2 /d) of the candidat...
Image
Core channel grouping in CATHENA model for the Canadian SWR-SMR

Core channel grouping in CATHENA model for the Canadian SWR-SMR

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 11 Core channel grouping in CATHENA model for the Canadian SWR-SMR More about this image found in Core channel grouping in CATHENA model for the Canadian SWR-SMR
Image
Schematic of CATHENA hydraulics idealization for SCW-SMR

Schematic of CATHENA hydraulics idealization for SCW-SMR

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 12 Schematic of CATHENA hydraulics idealization for SCW-SMR More about this image found in Schematic of CATHENA hydraulics idealization for SCW-SMR
Image
Axial profiles of (a) coolant temperatures and (b) density

Axial profiles of ( a ) coolant temperatures and ( b ) density

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 13 Axial profiles of ( a ) coolant temperatures and ( b ) density More about this image found in Axial profiles of ( a ) coolant temperatures and ( b ) density
Image
Core power distributions for case I (left) and case II (right)

Core power distributions for case I (left) and case II (right)

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 14 Core power distributions for case I (left) and case II (right) More about this image found in Core power distributions for case I (left) and case II (right)
Image
CATHENA predicted maximum fuel cladding temperatures for case I (left) and case II (right)

CATHENA predicted maximum fuel cladding temperatures for case I (left) and ...

Open Access
in Progress on a Preconceptual Supercritical Water-Cooled Small Modular Reactor > Journal of Nuclear Engineering and Radiation Science
Published Online: May 8, 2025
Fig. 15 CATHENA predicted maximum fuel cladding temperatures for case I (left) and case II (right) More about this image found in CATHENA predicted maximum fuel cladding temperatures for case I (left) and ...