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Journal Articles

A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset

Lorenzo Loi, Stefano Lorenzi, Antonio Cammi, Carolina Introini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. January 2024, 10(1): 014502.
Paper No: NERS-23-1029
https://doi.org/10.1115/1.4064308
Published Online: December 22, 2023
View Article titled, A Monte Carlo Fuel Assembly Model Validation Adopting Post Irradiation Experiment Dataset
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Topics: Cycles, Fuels, Irradiation (Radiation exposure), Manufacturing, Nuclides, Simulation, Temperature, Uncertainty, Geometry, Errors
Journal Articles

Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code

Xingyu Zhao, Minyun Liu, Rongyi Cui, Shanfang Huang, Kan Wang, Chuan Lu
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2023, 9(4): 041103.
Paper No: NERS-22-1137
https://doi.org/10.1115/1.4056772
Published Online: May 31, 2023
View Article titled, Optimized Moderator Design and Analysis of a Pin-Type Supercritical Carbon Dioxide Reactor Based on Reactor Monte Carlo Code
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Topics: Coolants, Design, Diluents, Fuels, Leakage, Neutrons, Supercritical carbon dioxide, Nuclear fission, Nuclides, Feedback
Journal Articles

Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation

Branislav Vrban, Štefan Čerba, Jakub Lüley, Filip Osuský, Vladimír Nečas
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041502.
Paper No: NERS-21-1010
https://doi.org/10.1115/1.4051613
Published Online: March 16, 2022
View Article titled, Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation
Open the PDF for Cross Section and Fission Yields Induced Uncertainty in the Water–Water Energetic Reactor-440 Burnup Calculation in another window
Topics: Fuels, Nuclear fission, Uncertainty, Water, Nuclides, Neutrons
Journal Articles

The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term

Riku Tuominen, Ville Valtavirta
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. October 2022, 8(4): 044503.
Paper No: NERS-21-1019
https://doi.org/10.1115/1.4051445
Published Online: March 15, 2022
View Article titled, The Effect of Serpent 2 Calculation Parameters on Evaluated Spent Nuclear Fuel Source Term
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Topics: Boiling water reactors, Emissions, Heat, Manufacturing, Nuclear fission, Photons, Probability, Resonance, Spent nuclear fuels, Nuclides
Journal Articles

Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2

Silja Häkkinen
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2022, 8(4): 041901.
Paper No: NERS-21-1015
https://doi.org/10.1115/1.4051444
Published Online: March 15, 2022
View Article titled, Impact of Approximations in Operating History Data on Spent Fuel Properties With Serpent 2
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Topics: Approximation, Coolants, Cycles, Irradiation (Radiation exposure), Manufacturing, Nuclides, Spent nuclear fuels, Heat, Boron, Photons
Journal Articles

Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator

Muhammad Aadil, Rab Nawaz, Ajmal Shah, Kamran Rasheed Qureshi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2022, 8(2): 021801.
Paper No: NERS-20-1210
https://doi.org/10.1115/1.4051618
Published Online: October 19, 2021
View Article titled, Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator
Open the PDF for Numerical Study of the Deposition of Radioactive Nuclide (Aerosol) in Pressurized Water Reactor Steam Generator in another window
Topics: Aerosols, Boilers, Decontamination, Nuclides, Particulate matter, Pressurized water reactors, Turbulence, Computational fluid dynamics, Flow (Dynamics), Particle size
Journal Articles

Prediction of Potential Offsite TEDE, Excess Cancer Risk, Dominant Exposure Pathways, and Activity Concentration for Hypothetical Onsite Soil Contamination at the Proposed Rooppur Nuclear Power Plant

Md. Ashraful Islam, Md. Hossain Sahadath
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Technical Briefs
ASME J of Nuclear Rad Sci. July 2021, 7(3): 034502.
Paper No: NERS-20-1033
https://doi.org/10.1115/1.4048123
Published Online: February 19, 2021
View Article titled, Prediction of Potential Offsite TEDE, Excess Cancer Risk, Dominant Exposure Pathways, and Activity Concentration for Hypothetical Onsite Soil Contamination at the Proposed Rooppur Nuclear Power Plant
Open the PDF for Prediction of Potential Offsite TEDE, Excess Cancer Risk, Dominant Exposure Pathways, and Activity Concentration for Hypothetical Onsite Soil Contamination at the Proposed Rooppur Nuclear Power Plant in another window
Topics: Agricultural pollution, Cancer, Nuclear power stations, Radioisotopes, Risk, Soil, Nuclides
Journal Articles

Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing

Massimo Sarotto, Gabriele Firpo, Anatoly Kochetkov, Antonin Krása, Emil Fridman, Jerzy Cetnar, Grazyna Domanska
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2020, 6(1): 011402.
Paper No: NERS-18-1132
https://doi.org/10.1115/1.4044000
Published Online: November 29, 2019
View Article titled, Neutronic Analyses of the FREYA Experiments in Support of the ALFRED Lead-Cooled Fast Reactor Core Design and Licensing
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Topics: Design, Fast neutron reactors, Nuclear fission, Nuclides, Uncertainty, Uncertainty analysis, Licensing, Neutrons, Rods, Simulation
Journal Articles

A Study of Transverse Buckling Effect on the Characteristics of Nuclides Burnup Wave in a Fast Neutron Multiplying Media

Manish Kumar, Om Pal Singh
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. October 2019, 5(4): 041401.
Paper No: NERS-18-1007
https://doi.org/10.1115/1.4043294
Published Online: July 19, 2019
View Article titled, A Study of Transverse Buckling Effect on the Characteristics of Nuclides Burnup Wave in a Fast Neutron Multiplying Media
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Topics: Neutrons, Waves, Nuclides, Buckling, Leakage, Transients (Dynamics)
Journal Articles

Breeding Properties Study on High-Power Thorium Molten Salt Reactor

Yafen Liu, Rui Guo, Xiangzhou Cai, Rui Yan, Yang Zou, Bo Zhou
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011003.
Paper No: NERS-17-1151
https://doi.org/10.1115/1.4041272
Published Online: January 24, 2019
View Article titled, Breeding Properties Study on High-Power Thorium Molten Salt Reactor
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Topics: Fuels, Molten salt reactors, Nuclides, Security, Temperature, Transients (Dynamics), Fluids, Nuclear fission, Graphite
Journal Articles

Calibration of HPGe Detector Efficiencies With Self-Absorption Correction of Gas Sphere Sources

Waseem Khan, Chaohui He
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. January 2019, 5(1): 011018.
Paper No: NERS-18-1038
https://doi.org/10.1115/1.4041338
Published Online: January 24, 2019
View Article titled, Calibration of HPGe Detector Efficiencies With Self-Absorption Correction of Gas Sphere Sources
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Topics: Absorption, Sensors, Photons, Calibration, Nuclides, Simulation, Density
Journal Articles

Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code

Jian Li, Ding She, Lei Shi
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2018, 4(2): 021007.
Paper No: NERS-17-1089
https://doi.org/10.1115/1.4038771
Published Online: March 5, 2018
View Article titled, Research on MMPA Algorithm for Solving Detailed Depletion Chain With the NUIT Code
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Topics: Algorithms, Chain, Errors, Nuclides, Polynomial approximation, Physics
Journal Articles

Methodology to Design Simulated Irradiated Fuel by Maximizing Integral Indices (ck, E, G)

Jason R. Sharpe, Adriaan Buijs, Jeremy Pencer
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021017.
Paper No: NERS-15-1079
https://doi.org/10.1115/1.4031074
Published Online: February 29, 2016
View Article titled, Methodology to Design Simulated Irradiated Fuel by Maximizing Integral Indices (ck, E, G)
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Topics: Design, Fuels, Isotopes, Nuclear fission, Optimization, Spent nuclear fuels, Supercritical water reactors, Uncertainty, Density, Nuclides
Journal Articles

Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration

Davide Chersola, Guglielmo Lomonaco, Guido Mazzini
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. July 2015, 1(3): 031004.
Paper No: NERS-14-1027
https://doi.org/10.1115/1.4029521
Published Online: May 20, 2015
View Article titled, Cross-Section Influence on Monte Carlo-Based Burn-Up Codes Applied to a GFR-Like Configuration
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Topics: Cross section (Physics), Density, Flux (Metallurgy), Fuels, Nuclides, Spectra (Spectroscopy), Nuclear fission, Fast neutron reactors