OOIR: Observatory of International Research

Papers

(The TQCC of Nuclear Science and Engineering is 2. The table below lists those papers that are above that threshold based on CrossRef citation counts [max. 250 papers]. The publications cover those that have been published in the past four years, i.e., from 2021-06-01 to 2025-06-01.)

Article	Citations
Stability and Performance of the X-CMFD Method for Multiphysics Reactor Calculations	70
Uncertainty Quantification of ²³⁷ Np, ²⁴¹ Am, and ²⁴³ Am Reaction Rates in Highly Enriched Uran	21
A New Calculation Method Using Pathlines for Delayed Neutron Precursors in Liquid Nuclear Fuels	17
High-Order Accurate Solutions of the Point Kinetics Equations with the Spectral Deferred Correction Method	13
LQG/LTR Controller Design for Power Control of Small Pressurized Water Reactors Under Four Feedback-Controlled Strategies	13
Advances in Nuclear Data and Software Development for the HighNESS Project	12
Modeling Interface Debonding in Coated Fuel Particles with BISON	11
Analysis of Major Benchmark Uncertainties for Fast Metal Assemblies in the ICSBEP Handbook	11
Proposed Enhancements to the Risk-Informed and Performance-Based Regulatory Framework for Seismic Hazard Design at NRC-Regulated Nuclear Power Plants	10
Decay Dose Shielding Analysis with Hybrid Unstructured Mesh/Constructive Solid Geometry Monte Carlo Calculation and ADVANTG Acceleration	10
Kinetic Theory Study of Pressure and Equation of State in a Strongly Degenerate Fermi Gas	10
The NILO-CMFD Method for Iteratively Solving Coupled Neutron Transport–Thermal Hydraulics Problems	10
The Effects of Curved Gas-Liquid Interface on Light Reflectance Liquid Film Measurement for an Optical Waveguide Film	10
A New Era of Nuclear Criticality Experiments: The First 10 Years of Flattop Operations at NCERC	10
Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor	9
On the Feasibility of a RGA-Based Decoupling Control in the Reactor-Follow-Turbine Operation of a PWR	9
Coupling Fixed-Source Criticality or Criticality and Shielding Modes Within TRIPOLI-4® Monte Carlo Code	9
Analysis of Stress Corrosion Cracking Growth Rate in the Heat-Affected Zone of 316L Based on the Heterogeneity of the Mechanical Properties	9
A Stochastic Calculus Approach to Boltzmann Transport	9
In Situ Electronic Structure Analysis of Water-Corroded UN _x in High Vacuum	9
Analytic Error Analysis of the Partial Derivatives Cross-Section Model—I: Derivation	8
A Study of the Spatially Developing Laminar-Turbulent Transition in Rod Bundles	8
Numerical Simulations of Passive Heat Removal from Mobile Microreactors	8
Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research Reactor Core for Fluid Flow Optimization Using a Channel Box	8
OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model	8

Multigroup Neutron Transport Using a Collision-Based Hybrid Method	8
MOOSE Reactor Module: An Open-Source Capability for Meshing Nuclear Reactor Geometries	8
Multistep Criticality Search and Power Shaping in Nuclear Microreactors with Deep Reinforcement Learning	7
Estimation of Near-Field and Far-Field Post-Accident Atmospheric Dispersion for Microreactors	7
Study on Fission Decay Width of Superheavy Nuclei ²⁹⁸ 119 Synthesized through the Various Fusion Reactions	7
A New Calculation Strategy for Molten Salt Reactor Neutronic–Thermal-Hydraulic Analysis Implemented with APOLLO3® and TRUST/TrioCFD	7
Statistical Study of Stress and Strain in Matrix of UO ₂ -Zr Plate Type Fuel	7
A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup Neutron Transport Simulations	7
Investigations of Multiphysics Models on a Megawatt-Level Heat Pipe Nuclear Reactor Based on High-Fidelity Approaches	7
Variance Reduction and Noise Source Sampling Techniques for Monte Carlo Simulations of Neutron Noise Induced by Mechanical Vibrations	7
Reactivity Impact of Updated ³⁵ Cl Nuclear Data on the Molten Chloride Reactor Experiment	7
An Asymptotic-Preserving Hybrid Angular Discretization for the Gray Radiative Transfer Equations	7
Unsupervised Learning for Improved Gamma-Ray Spectrometry in Pixelated Cadmium Zinc Telluride (CZT) Detectors	7
Assessment of Modeling Decisions for Depletion Multiphysics Studies of AHTR	7
The Effect of Branchless Collisions and Population Control on Correlations in Monte Carlo Power Iteration	7
Implementation and Testing of Generalized Perturbation Theory Capabilities in TRIPOLI-4®	6
One-Dimensional Drift Flux Analysis of Bubbly Flows in Horizontal and Inclined-Upward Orientations	6
Comparative Analysis of Standard and Advanced USL Methodologies for Nuclear Criticality Safety	6
Measurements of Droplet Size and Velocity Distributions During Rod Bundle Core Reflood	6
Lagrangian Investigation of Convective Mass Transfer of Dissolved Elements at Specimen Boundaries in a Flowing Molten Lead Loop	6
Simulation Analysis Based on Sodium-Cooled Fast Reactor Fuel Assembly Under Blockage Accident	6
Probability Density Functions with Correlations of Experimental and Evaluated ²³⁵ U(n _th ,f) Fission Yields and Their Impacts on R	6
Utilizing Sensitivity and Correlation Coefficients from MCNP and Whisper to Guide Microreactor Experiment Design	6
Research and Application of the Rehomogenization Method for PWR Core Neutron Physics Simulation	6
Measurements of Neutron Scattering from a Copper Sample Using a Quasi-Differential Method in the Region from 2 keV to 20 MeV	6
Performance Improvement of Weight Window Method by Incorporating DXTRAN	6
Pre-Experimental Assessment of Uranyl Nitrate Solution Irradiation in Kartini Reactor Facilities	6
Tool Developments in the OpenMC Code: Correlated Sampling and Transient Fission Matrix Approach Coupled to OpenFOAM	6
Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach During Transient Operation	6
Development of a TRACE Critical Break LOCA Model for D-PSA Applications with RAVEN	6
On the Accuracy of Transport Spatial Discretization Methods for Diffusive Regimes	6
Numerical Investigation of Process Parameter Effects on Flow Oscillations in a Natural Circulation Boiling Integral PWR-Type SMR Test Rig	6
The Solitary Wave in Advanced Nuclear Energy System	5
A 2-D Physics Study for Understanding Moderator Temperature Coefficient of Burnable Absorber–Loaded Prismatic High-Temperature Helium-Cooled Reactor	5
Demonstrating a Quantitative and Systematic Approach to Reducing Excess Conservativism in Nuclear Criticality Safety Analyses	5
Coupling Nuclear Predictions into Damage Simulations with SPECTRA-PKA	5
Analysis of the Use of Different Backing Layer Materials in the Design of Alpha-Decay Sails for Interplanetary and Interstellar Travel	5
Magnetohydrodynamic Analyses of a Miniature, Dual-Stage Electromagnetic Pump for Lead and Sodium In-Pile Test Loops	5
Improvements in Antineutrino Spectrum by Including Fission Product Corrections and Calculation of Scatter-Based Pulse Height Distributions	5
Volume Mesh–Based Monte Carlo Particle Transport with Barycentric Particle Tracking	5
Development of Conceptual Lead Cartridge Design to Perform Irradiation Experiments in VTR	5
Uncertainty Benchmarks for Time-Dependent Transport Problems	5
Dismantling and Clearance Approach for the Swiss Light Source (SLS)	5
Space-Dependent Calculation of the Multiplicity Moments for Shells With the Inclusion of Scattering	5
Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT for Hexagonal Geometry Core Multiphysics Analysis	5
A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants	5
Interaction of Cesium Hydroxide with Oxide Layers Under Simulated Light Water Reactor Severe Accident	5
Investigations of Suction Recirculation in Primary Sodium Pump of Future Indian Fast Breeder Reactors	5
Alkaline Hydrolysis of Tri-iso-amyl Phosphate in n-dodecane Using Sodium Hydroxide: Part 1—Factors Affecting the Hydrolysis Process	5
Effect of Internal Decay Power and Surface Cooling on Nuclear Fuel Droplet Solidification During MFCI in a SFR—A Numerical Study	5

Design and Development of the 200-kW Beam Dump	5
Safety Analysis in VVER-1000 Due to Large-Break Loss-of-Coolant Accident and Station Blackout Transient Using RELAP5/SCDAPSIM/MOD3.5	4
Measurements of the Neutron Total and Capture Cross Sections and Derivation of the Resonance Parameters of ¹⁸¹ Ta	4
A Study of Gamma Heating, Neutron Flux, and Gamma Flux Under Several Reactor Core Conditions in the McMaster Nuclear Reactor	4
State of the Art in Cyclotrons for Radionuclide Production in Biomedicine	4
Radiation Protection at Petawatt Laser-Driven Accelerator Facilities: The ELI Beamlines Case	4
Resolved Resonance Evaluation for Neutron Interactions with ¹⁰³ Rh up to 8 keV	4
Analyzing APR1400 System Response Under Load Follow Operation Using a Multiphysics Approach	4
Some Considerations on the Equations Employed to Describe Multiplicity Moments	4
On the Uncertainty Analysis of the Data-Enabled Physics-Informed Neural Network for Solving Neutron Diffusion Eigenvalue Problem	4
Developing a Deterministic Calculation Scheme for Perturbations of In-Core Instrumentation of an MTR Core in Support of Bayesian Calibration	4
Numerical Simulation of Turbulent Flow and Friction Characteristics Through a Loop of Narrow Rectangular Channel Under Rolling Motions	4
Data-Enabled Physics-Informed Machine Learning for Reduced-Order Modeling Digital Twin: Application to Nuclear Reactor Physics	4
Development, Verification, and Validation of an Advanced Systems Code KP-SAM for Kairos Power Fluoride Salt–Cooled High-Temperature Reactor (KP-FHR)	4
Scoping Analysis of Pebble-Bed Reactors for the Destruction of the Transuranic Inventory of LWR Spent Nuclear Fuel	4
Design and Analyses of Miniature, Submersible Annular Linear Induction Pump for Test Loops Supporting Development of Advanced Nuclear Reactors	4
First Order Response Matrix Benchmark for the 1D Transport Equation with Matrix Scaling	4
On the Role of Axial Neutron Flux Mode Excitation in BWR Stability and Nonlinear Oscillations	4
A Parallel Coloring Newton-Krylov Method for Multiphysics Coupling System in Nuclear Reactors	4
Generalized Integral Method for Solving the Neutron Transport Equation with the Hybridized Discontinuous Galerkin Method	4
DOE Robot Perspective: Past, Present, and Future	4
High-Order Perturbation Method for Updating Response Functions for Time-Dependent Transport Calculations	4
Uncertainty Analysis of the Reaction Rates in Ringhals	4
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of ²⁴¹ Pu	4
Accelerator Technology for Well Logging: Advances, Challenges, and Opportunities	4
Estimation of ¹³⁷ Cs Contamination Density of Wall, Ceiling, and Floor at Unit 2 Operation Floor in Fukushima Daiichi Nuclear Power Station Using Pinhole Gamma Camer	4
Implementation of Resonance Upscattering Treatment in FRENDY Nuclear Data Processing System	4
Selected papers from the 17th International Topical Meeting on Probabilistic Safety Assessment and Analysis (PSA 2021)	4
Preference-Based Multi-Robot Planning for Nuclear Power Plant Online Monitoring and Diagnostics	4
Void Reactivity in Lead and Bismuth Sample Reactivity Experiments at Kyoto University Critical Assembly	4
Reactor Physics Monitoring of a Source-Driven Subcritical System in Stationary State by Deterministic and Probabilistic Deep Neural Networks	4
A General Formulation of the Resonance Spectrum Expansion Self-Shielding Method	4
Analysis of Corner Balance Nonlinear Diffusion Acceleration and Moment-Based, Spatially Linear Transport Discretizations	4
Direct Numerical Simulation of High Prandtl Number Fluid Flow in the Downcomer of an Advanced Reactor	4
Axial Power Distribution Using Improved Axial Reflector Constants Calculation	4
Two-Step Monte Carlo Calculation Method for Sensitivity Coefficients of Reactor Period with Respect to Kinetics Parameters	4
Fuel Cycle Performance of the Wielenga Innovation Static Salt Reactor	4
Spherical Harmonics and Discontinuous Galerkin Finite Element Methods for the Three-Dimensional Neutron Transport Equation: Application to Core and Lattice Calculation	4
High-Order Finite Element Second Moment Methods for Linear Transport	4
Preparation and Electrical Performance Analysis of a GaAs‐Based Tritium Battery	3
Moment Asymptotics for the Neutron Transport Equation	3
Development of a Coupled Depletion Perturbation Theory Methodology in Continuous-Energy Monte Carlo Depletion Simulations	3
A Study of Nuclear Fuel Burnup Wave Development in a Fast Neutron Energy Spectrum Multiplying Medium: Improved Model and Consistent Parametric Approach for Evaluation	3
Activation Analysis in Preparation for a Tungsten Irradiation Experiment at LANSCE	3
Morphological Characterization of Uranyl Fluoride Particles via Atomic Force Microscopy	3
COAL Experiments Investigating the Reflooding of a 7 × 7 Rod Bundle During a Loss-of-Coolant Accident: Effect of a Partially Blocked Area with Ballooned Rods	3
Convergence Properties of a Linear Diffusion-Acceleration Method for k-Eigenvalue Transport Problems	3
Application of MELCOR for Simulating Molten Salt Reactor Accident Source Terms	3
Feasibility of Photonuclear Transmutation of Long-Lived Fission Products Extracted from Used Nuclear Fuel	3
A Method to Calculate the Maturity Time for Low Neutron Source Nuclear Reactor Startup Simulations	3
Optimizations of the Accelerated Axial Polynomial Method of Characteristics of the APOLLO3® Deterministic Neutron Transport Code	3
The Versatile Test Reactor Project: Mission, Requirements, and Description	3
Application of Accelerator Beam Dumps for Dark Matter Searches	3
Optimizing Hydride Stability in U-ZrH _x Nuclear Fuel: The “Goldilocks Radius”	3
Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor: Instrumentation and Measurement—Part II	3
A Pragmatic Approach to Update Support Studies and Human Reliability Analyses for a PSA Model	3
An Experimental Investigation of Two-Phase Frictional Pressure Drop in Straight-Tube Steam Generator Used in SFR	3
Ionization Efficiency Measurement and Optimization of a Thermal Ion Source for Radioisotope Electromagnetic Separation	3
An Attention-Based CNN-LSTM Model to Diagnose Break Size in Loss-of-Coolant Accidents	3
Study on Logging Identification of Sandstone-Type Uranium Deposits Based on Ensemble Learning in the Songliao Basin in Northeast China	3
Stress Profile in Coating Layers of TRISO Fuel Particles in Contact with One Another	3
Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation	3
An Iterative RSA-DEM Method for High Particle Packing Fraction Stochastic Media	3
Comparison of ²³⁸ U and ²³⁵ U Fission Chambers for Monitoring the Reactivity of the VENUS-F Accelerator-Driven Subcritical Reactor	3
Preliminary Neutronics Design and Analysis of the Fast Modular Reactor	3
Neutron Noise Measurements of a Fast HEU Copper System	3
An Improved Dual Asymmetric Penalized Least Squares Baseline Correction Method for High-Noise Spectral Data Analysis	3
A Consequence-Informed Licensing Path Selection for the Design of Physical Protection Systems at Commercial Nuclear Power Facilities	3
Applicability of Dynamic Mode Decomposition to Estimate Fundamental Mode Component of Prompt Neutron Decay Constant from Experimental Data	3
Investigations of Gamma and Neutron Shielding Parameters of Ti-Nb-Fe-Cr Alloys with Varying Cr Concentrations	3
Identification of Important Phenomena for Light Water Reactors During Heat Transport System Failure Events in Integrated Energy Systems	3
Development and Validation of Thermal-Mechanical Creep Failure Module for Reactor Pressure Vessel Lower Head	3
A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation	3
Influence of Quantum Oscillations in the Thermal Scattering Law of Zirconium Carbide on Neutron Thermalization and Criticality	3
New Measurements to Resolve Discrepancies in Evaluated Model Parameters of ¹⁸¹ Ta	3
Exponential Time Differencing Schemes for Fuel Depletion and Transport in Molten Salt Reactors: Theory and Implementation	3
Effect of Backing on Neutron Spectra for Low-Energy Quasi-Monoenergetic p + ⁷ Li Reaction	3
Comparing Coupled Multiphysics Simulations of Pump-Driven Transients for a Pressurized Heavy Water Reactor	3
Computationally Optimized Irradiation Chamber Design for Production of ¹³⁵ Xe in the Washington State University TRIGA Reactor	3
Combining Similarity Measures and Left-Right Hidden Markov Models for Prognostics of Items Subjected to Perfect and Imperfect Maintenance	3

On the Numerical Method for Photofission-Based Nuclear Material Isotopic Composition Estimation in Thorium-Uranium Systems	2
Flow-Induced Vibrations of Two Flexible Tubes in Cross Flow	2
Advanced Liquid-Metal-Cooled Fast Reactor Core Design Using Modern Optimization Algorithms	2
The Finite-Element with Discontiguous-Support Method	2
CANDU Station Blackout D-PSA with RAVEN and TRACE Software	2
CFD Investigations to Understand Thermal Performance of Helically Rifled Heat Transfer Enhancements in Molten Salt Applications	2
On the Assumptions Behind Statistical Sampling: A ²³⁵ U Fission Yield Uncertainty Propagation Case Study	2
CFD Simulation of Melt Pool Coolability in a Simulated Core Catcher Model	2
Research on Nuclear Power Plant Operational Task Complexity Assessment Method Based on Group Decision Making and Deep Learning of EEG Signals	2
Impact Assessment of Radiative Heat Transport in ARC-Class Reactor FLiBe Liquid Immersion Blanket	2
Effects of Temperature and Electron Energy on the Defect Evolution Behavior of Pristine and Ion-Irradiated Yttria-Stabilized Zirconia	2
ADDENDUM: Validation of Continuous-Energy ENDF/B-VIII.0 ¹⁶O, ⁵⁶Fe, and ^63,65Cu Cross Sections for Nuclear Criticality Safety Applications	2
Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO ₂ Fuel	2
Recent Advances in the Fenton Process for Treatment and Volume Reduction of Liquid Radioactive Waste	2
Numerical Investigation on the Thermal-Hydraulic Characteristics near a Corroded Lower Head of the Reactor Vessel During IVR-ERVC	2
A Consistent Low-Order Acceleration Technique for Coarse Mesh Transport (COMET) Methods	2
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of²⁴⁵Cm	2
Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts	2
Special issue featuring papers from the 2023 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2023) Guest Editors	2
Improvements to the Baff-Refl Equivalence Technique Applied to Reflector Models in PWRs	2
MaCaw: Domain-Decomposed Monte Carlo Neutral Particle Transport on Unstructured Mesh in MOOSE	2
Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)	2
Early-Stage Radiation Safety Analysis for the Spallation Neutron Source Second Target Station Bunker Operations	2
Nonconforming Three-Dimensional Model for PWR Control Rod Movements Without Homogenization and Cusping Effect	2
Measurement of the Prompt Neutron Decay Constant in a Zero-Power Reactor Using a Novel 3D Detector System	2
A Practical Comparison of Data-Driven Prognostics Methods for Energy Systems	2
Establishment of Control Room Habitability Analysis Methodology Postulating the Event of Pressurized Tank/System of Hazardous Gas Release	2
Monte Carlo Calculation Method for Reactor Period Utilizing the Differential Operator Sampling Technique	2
Few-View CT Image Reconstruction via Least-Squares Methods: Assessment and Optimization	2
Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled Fast Molten Salt Reactors	2
Two-Phase Turbulent Kinetic Energy Budget Computation in Co-Current Taylor Bubble Flow	2
Scoping Studies for a Lead-Lithium-Cooled, Minor-Actinide-Burning, Fission-Fusion Hybrid Reactor Design	2
A Novel ERANOS Procedure for Sensitivity Analyses in Core Depletion Problems: Implementation Details and Verification	2
Dynamical System Scaling Application to Zircaloy Cladding Thermal Response During Reactivity-Initiated Accident Experiment	2
A Residual-Based Subgrid-Scale Method Combined with Spherical Harmonics Angular Approximation for Solving the Boltzmann Transport Equation	2
Continuous-Energy ENDF/B-VIII.0 Cross Section and SCALE 6.2.4 Performance for Nuclear Criticality Safety Applications: ¹H, C, ^58,60Ni, ^{182,183,184,186}W, ^235,238	2
Integrated Safety and Security Analysis of Nuclear Power Plants Using Dynamic Event Trees	2
Core Reload Design Using Genetic Optimization for Cost Savings in a Two-Reactor Power Plant With Used Fuel Sharing	2
Bayesian Estimation of Cross Section, Experimental Error, and Calculation Error: Comparison with Bias Factor Method	2
Derivation of Uncertainty Distributions for Channel Flow Rate and Fuel Critical Heat Flux Predictions for Best-Estimate Plus Uncertainty Analysis of Slow Loss-of–Reactor Power Regulation Accidents in	2
Gas-Liquid Two-Phase Flow Regime in a Horizontal Channel Under Transverse Vibration	2
Numerical Investigation of Air-Steam Condensation in a Vertically Enhanced Tube with Concave and Convex Surfaces	2
Development of Uncertainty Analysis Techniques for the Fission Matrix–Based Neutron Transport Code RAPID	2
Current State of the Design Engineering of the Versatile Test Reactor Plant	2
Using a Random Forest Model to Choose Optimized Group Structures	2
Optimization of Personnel Work Paths During Decommissioning of Nuclear Facilities	2
Low-Temperature MOCVD Deposition of Vanadium Carbide on F/M Steel for Mitigating Fuel-Cladding Chemical Interaction	2
A Novel High-Order Surface Characteristics Scheme for the Neutron Transport Equation in 2D Unstructured Meshes	2
Experimental Estimation of the Kinetic Parameters of MINERVE Zero Power Reactor	2
Three-Dimensional Thermal Modeling of In Situ Heating Tests for High-Level Radioactive Nuclear Waste Repository	2
Thermodynamic Assessment of the NaCl-CrCl ₂ , NaCl-CrCl ₃ , and FeCl ₂ -CrCl ₂	2
Hybrid Variable Selection for Estimating Nominal HEPs and PIF Multipliers for Digital Control Rooms	2
Experimental Analyses of Capture Reaction Rates for Epithermal and Resonance Neutrons in Source-Driven Subcritical Cores	2
Modeling of Formation and Evolution of Cracks in Zirconium-Based Claddings of Nuclear Fuel Rods Within DIONISIO 3.0	2
Evaluating Quantities of Interest Other Than Nuclide Densities in the Bateman Equations	2
Technical Reviewers	2
Linear Source Approximation in MPACT for Efficient and Robust Multiphysics Whole-Core Simulations	2
Welch Method and Bootstrapping Applied to Subcritical Gamma Noise	2
Physics-Informed Neural Networks for 1-D Steady-State Diffusion-Advection-Reaction Equations	2
Strategies for Fast Fission Matrix Estimation with Fuel Temperature and Control Rod Feedback	2
Designing the Second Target Station with a Coupled Neutronics-Mechanical Optimization Workflow	2
Charge Distribution Studies in the Epi-Cadmium Neutron-Induced Fission of ²⁴¹ Pu	2