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Division Spotlight
Young Members Group
The Young Members Group works to encourage and enable all young professional members to be actively involved in the efforts and endeavors of the Society at all levels (Professional Divisions, ANS Governance, Local Sections, etc.) as they transition from the role of a student to the role of a professional. It sponsors non-technical workshops and meetings that provide professional development and networking opportunities for young professionals, collaborates with other Divisions and Groups in developing technical and non-technical content for topical and national meetings, encourages its members to participate in the activities of the Groups and Divisions that are closely related to their professional interests as well as in their local sections, introduces young members to the rules and governance structure of the Society, and nominates young professionals for awards and leadership opportunities available to members.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Below is a listing of the learning objectives for each module in the program.
Introduction to the Nuclear PE Exam
Registering for the Exam
Preparations for the Exam
General Information
Nuclear History
Agencies, Regulators, and Professional Organizations (PDF only)
Science Background
Introduction to Units (PDF only)
This topic also includes the following modules (PDFs only):
-Unit Conversions: Nuclear Physics and Basic Units
-Unit Conversions: Flow Calculations
-Unit Conversions: Energy and Power
-Constants and Units
Fundamentals of Nuclear Structure
Fundamental Particles
The Electron
Waves and Particles
Relativity and Time Dilation
Length Contraction
Cerenkov Radiation
Analysis
Chart of the Nuclides
Atom Density Calculations, Part I
Atom Density Calculations, Part II
Atom Density Calculations, Part III
Nuclear Reactions
Binding Energy
Threshold Energy
Nuclear Stability and X-Rays
Radioactive Decay
Radioactive Decay Overview
Alpha and Beta Decay
Positron Decay and Electron Capture
Activity and Decay Rate
Decay Chains
Isotope Production and Decay Summary
Energy Deposition
Interactions of Heavy Charged Particles
Ranges and Heavy Charged Particles
Range of Alpha Particles
Interactions of Electrons
-Excitation and ionization.
-Bremsstrahlung.
Stopping Power of Electrons
Bremsstrahlung
Range of Electrons
Range of Electrons Examples
Interaction of Photons with Matter
Particle Interactions
Photon Interactions Overview
-Photoelectric effect
-Compton scattering
-Pair production
Photoelectric Effect
Compton Scattering
Pair Production
Photon Interaction Coefficients
Measuring Attenuation Coefficients (Mu)
Photon Cross Sections
Absorption Cross Sections
Process Cross Sections
Radiation Detection and Dosimetry
Radiation Detection
Ionization Chambers and Proportional Counters
Gas-Filled Counters
Semiconductor Detectors
Scintillation Detectors
Radiation Dosimetry
Radiation Dosimetry Topics
Radiation Dosimetry Examples
Internal Dosimetry
Internal Half-Lives
Annual Limit on Intake (ALI) and Derived Air Concentration (DAC)
Dose Assessment and Personnel Safety
Biological Effects of Radiation
Threshold Dose
Dose Limits
Dose Topics
Shielding
External Radiation Protection and Shielding
Geometry of Shielding
Determination of Buildup Factors
Shielding Analysis
Shielding Examples, Part I
Shielding Examples, Part II
Photon Shielding Principles
Nuclear Fuel Cycle Front End
Nuclear Fuel Cycle: Front End
– the purpose of each component of the open nuclear fuel cycle.
– how to perform material balance problems.
– how to perform separative work problems.
– how to calculate the cost of enrichment.
Enrichment: Gaseous Diffusion
– the physics of gaseous diffusion enrichment and the associated equations.
– the details of a gaseous diffusion plant.
Enrichment: Gaseous Centrifugation
– the physics of gaseous centrifugation enrichment.
– how to calculate the separative capacity of a centrifuge.
– comparison of the efficiency and capabilities of diffusion enrichment and centrifugation enrichment.
Front End Examples
Fuel Design and Analysis
Depletion, Burnup, and Transmutation
Reactor Fuel Design
Burnable Poisons
Cladding
Fuel Assembly Fabrication
– fuel pellet production
– fuel rod production
– fuel assembly production.
Nuclear Fuel Cycle Back End
Classification of Radioactive Waste
Decay Heat from UNF
UNF Spent Fuel Pools
UNF Dry Cask Storage
Transportation of Radioactive Materials
Geologic Disposal of Radioactive Waste
Steam
Steam Properties
Fluid Parameters
Steam Tables Examples, Part I
Steam Tables Examples, Part II
Steam Tables Examples, Part III
Steam Tables Examples, Part IV
Fluids
Fluid Flow and Energy Balance
Pressure Head
Laminar and Turbulent Flow
Friction Factors
Determination of Friction Factor
Calculation of Friction Head
Pumps
Pumps: Introduction
Pump Head and Calculations
Pumps: Cavitation and NPSH
Pumps: Examples of NPSH Calculations
Pump Performance
Pump Operation
Pump Calculations: Examples, Part I
Pump Calculations: Examples, Part II
For a given system layout:
Heat Exchangers
Heat Exchangers: Introduction
Overall Heat Transfer Coefficient
Log Mean Temperature Difference
Shell-and-Tube Heat Exchangers
Shell-and-Tube Heat Exchanger Parameters
Shell-and-Tube Heat Exchanger Example
Shell-and-Tube Heat Exchanger Example Problems
Kinetics
Delayed Neutrons
Reactivity and Period
Point Kinetics and Prompt Behavior
System Time Behavior
Kinetics Example Problems
Fission Product Poisoning
Reactivity Coefficients and Transients
Neutronics and Criticality
Neutron Balance
One-Group Diffusion theory
Modified One-Group Diffusion Theory
Neutron Spectrum
Neutron Cross Sections
Neutron Cross Section Examples
Buckling Conversion
Criticality Control
Criticality Example Problem
Nuclear Reactions and Q-values
Nuclear Fission
Fission Products and Decay Heat
Inverse Multiplication
Note: This portion of the program is under construction. Users can find information on these topics in other study resources.
Design-Basis Analysis
Fuel Performance Analysis
Pellet-Clad Interaction
Core Thermal-Hydraulic Analysis
Critical Heat Flux
Departure from Nucleate Boiling
LOCA Transient Analysis
Long-Term Cooling
Non-LOCA Transient Analysis
Containment Performance
Technical Specifications
Safety Analysis Report
Environmental Impact Statement
Probabilistic Risk Assessment and Severe Accident Analysis
Probabilistic Risk Assessment: Introduction
Basic Concepts of Probability
Probability Operations
Probability Models
Event and Fault Trees
Fault Tree Example
PRA Example Problems
Uncertainty Analysis
Reliability Analysis
Station Blackout
Core Damage Frequency
Risk Mitigation Systems
Severe Accident Phenomena
Last modified March 2, 2022, 1:46pm CST