Neutron Fluence Calculator

Model exposure with area, time, and spectrum options. See results above the form instantly here. Download tables to share with teams and audits today.

Calculator

Tip: Use consistent geometry and account for detector area or beam footprint.
Total neutrons recorded during exposure.
Beam footprint or detector active area.
Average flux over the exposure period.
Duration of irradiation or counting interval.
Use when fluence is measured or specified.

Uncertainty inputs (optional, %)

Enter relative 1σ uncertainties to estimate output uncertainty for products or ratios.
Results appear above after submission.

Formula Used

Neutron fluence Φ is the number of neutrons incident on a unit area.

  • Φ = N / A where N is total neutrons and A is irradiated area.
  • Φ = φ · t where φ is neutron flux (fluence rate) and t is exposure time.
  • φ = Φ / t for average flux over a known exposure duration.

Unit conversions are applied internally using SI base units (m², s) and then reported in both m² and cm² forms.

How to Use This Calculator

  1. Select a calculation mode based on your available measurements.
  2. Enter values with scientific notation if needed (example: 3.2e7).
  3. Choose correct units for area, flux, fluence, and time.
  4. Optionally add uncertainty percentages to estimate output uncertainty.
  5. Press Calculate to see results above the form.
  6. Use Download CSV or Download PDF for reporting.

Practical tip: For non-uniform beams, consider using the effective irradiated area that matches your detector response.

Example Data Table

Scenario Inputs Output (fluence) Notes
Count ÷ Area N = 2.0×108, A = 10 cm² Φ = 2.0×107 n/cm² Detector counted total neutrons over its active area.
Flux × Time φ = 5.0×105 n/cm²/s, t = 120 s Φ = 6.0×107 n/cm² Assumes average flux remains steady during exposure.
Fluence ÷ Time Φ = 1.2×109 n/cm², t = 10 min φ = 2.0×106 n/cm²/s Converts a specification into an average flux value.

Notes for Advanced Use

  • Geometry: Fluence depends on the area definition (beam spot vs detector area).
  • Time structure: For pulsed sources, use total integrated time or integrate per pulse.
  • Spectrum: If you need energy-dependent fluence, compute per energy bin and sum.
  • Uncertainty: The optional estimate uses root-sum-square for products and ratios.

Neutron Fluence Guide

1) Why neutron fluence matters

Neutron fluence (Φ) quantifies cumulative neutron exposure per unit area. It is widely used in radiation effects testing, shielding verification, activation planning, and detector calibration. Unlike dose, fluence tracks particle count, making it ideal for material damage or displacement metrics.

2) Typical units and magnitudes

Fluence is reported as n/cm² or n/m². Many lab specifications and test reports use n/cm² because values are compact; 1 n/cm² = 1×104 n/m². It is common to express results using scientific notation, such as 3.5×108 n/cm² for short irradiation campaigns.

3) Flux versus fluence in practice

Flux (φ) is the rate form, typically in n/cm²/s. When the source is steady, fluence is found by integrating flux over time, which simplifies to Φ = φ·t. For time-varying beams, compute φ for each interval and sum the interval fluences.

4) Geometry and beam footprint

The same neutron count produces different fluence values depending on the chosen area. A 2×108 neutron exposure over 10 cm² yields 2×107 n/cm², but over 1 cm² it becomes 2×108 n/cm². Use the effective irradiated area that matches your detector or sample footprint.

5) Detector and count corrections

If your count comes from a detector, consider efficiency, dead time, and background. For example, correcting 1.9×108 raw counts with a 95% efficiency gives a higher estimate of incident neutrons. Apply corrections before using the N/A mode.

6) Energy dependence and reporting

Many applications require energy-resolved fluence. A practical workflow is to compute fluence per energy bin and report both the integrated Φ and the bin table. This calculator focuses on integrated fluence, but it supports consistent unit conversions and clean export for reports.

7) Uncertainty and repeatability

Fluence derived from multiplication or division inherits uncertainty from each input. The optional uncertainty fields estimate a combined 1σ value using root-sum-square of relative uncertainties. This helps compare runs, evaluate stability, and communicate measurement confidence.

8) Quality checks before you export

Confirm units, verify that time corresponds to the same interval as flux or counts, and review geometry assumptions. If results differ by a factor of 104, it often indicates a cm² versus m² mismatch. Export CSV for calculations and PDF for audits.

FAQs

1) What is the difference between neutron fluence and neutron flux?

Fluence is the total neutrons per area accumulated over time. Flux is the rate, neutrons per area per second. For steady conditions, fluence equals flux multiplied by exposure time.

2) Which mode should I use if I only have detector counts?

Use Count ÷ Area. Enter total neutrons (corrected for efficiency if available) and the effective irradiated area. The calculator returns fluence in both n/m² and n/cm².

3) Why do my results change when I change the area?

Fluence is normalized to area. Smaller areas produce larger fluence for the same neutron count. Always use the actual beam footprint on the sample or the detector’s active area.

4) Can I use scientific notation like 1.2e9?

Yes. Inputs accept scientific notation such as 1.2e9 and values with decimals. This is helpful for large neutron fields where fluence and flux are commonly reported in powers of ten.

5) How is uncertainty estimated in this tool?

For products or ratios, the tool combines relative input uncertainties using root-sum-square and reports an estimated 1σ output uncertainty. It is a quick planning aid, not a substitute for a full uncertainty budget.

6) What units should I report in a lab note?

Use the unit requested by your procedure. Many test plans specify n/cm², while SI reporting may use n/m². This calculator provides both outputs to minimize transcription mistakes.

7) How do I handle pulsed or varying flux sources?

Compute fluence per pulse or per time interval and sum the contributions. If you only know an average flux over the full duration, you can still use Flux × Time as an approximation.

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