glossary:neutron-flux
CONCEPT dossier

Neutron Flux

Glossary term: Neutron Flux

CONCEPT Fusion Physics

01 Executive_Summary

The intensity of neutron radiation passing through a given area per unit time, typically measured in neutrons per square centimeter per second (n/cm²/s). In fusion reactors, neutron flux is a critical design parameter: high neutron flux degrades structural materials (neutron embrittlement) and activates reactor components. D-T fusion produces 14.1 MeV neutrons that require shielding and regular maintenance.

02 Definition

The intensity of neutron radiation passing through a given area per unit time, typically measured in neutrons per square centimeter per second (n/cm²/s). In fusion reactors, neutron flux is a critical design parameter: high neutron flux degrades structural materials (neutron embrittlement) and activates reactor components. D-T fusion produces 14.1 MeV neutrons that require shielding and regular maintenance.

03 Deep_Dive_Intelligence

Overview

The intensity of neutron radiation passing through a given area per unit time, typically measured in neutrons per square centimeter per second (n/cm²/s). In fusion reactors, neutron flux is a critical design parameter: high neutron flux degrades structural materials (neutron embrittlement) and activates reactor components. D-T fusion produces 14.1 MeV neutrons that require shielding and regular maintenance.

Role: Glossary term: Neutron Flux

Entity Type: Concept — Neutron Flux is a technical concept or theoretical framework.


Technical Definition

The intensity of neutron radiation passing through a given area per unit time, typically measured in neutrons per square centimeter per second (n/cm²/s). In fusion reactors, neutron flux is a critical design parameter: high neutron flux degrades structural materials (neutron embrittlement) and activates reactor components. D-T fusion produces 14.1 MeV neutrons that require shielding and regular maintenance.


Related Concepts: Aneutronic Fuel Cycle, Neutron Degradation, First-Wall Heat Flux, Superalloy

07 Key_Findings

  • Role: Glossary term: Neutron Flux
  • Entity Type: Concept — Neutron Flux is a technical concept or theoretical framework.
  • Related Concepts: Aneutronic Fuel Cycle, Neutron Degradation, First-Wall Heat Flux, Superalloy

10 FAQ

What is Neutron Flux?
The intensity of neutron radiation passing through a given area per unit time, typically measured in neutrons per square centimeter per second (n/cm²/s). In fusion reactors, neutron flux is a critical design parameter: high neutron flux degrades structural materials (neutron embrittlement) and activates reactor components. D-T fusion produces 14.1 MeV neutrons that require shielding and...
What role does Neutron Flux play in the research network?
Neutron Flux is classified under the "Fusion Physics" category, serving as Glossary term: Neutron Flux. The intensity of neutron radiation passing through a given area per unit time, typically measured in neutrons per square centimeter per second (n/cm²/s). In fusion reactors, neutron flux is a...
What evidence supports the Neutron Flux assessment?
The intelligence assessment for Neutron Flux is supported by 4 primary sources, 1 PDF document, and 1 citation. Key sources include "Neutron flux - Wikipedia", "Neutron flux - NRC Glossary", and "An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation". These documents provide the evidentiary basis for the analysis.
What is the technical definition of Neutron Flux?
The intensity of neutron radiation passing through a given area per unit time, typically measured in neutrons per square centimeter per second (n/cm²/s). In fusion reactors, neutron flux is a critical design parameter: high neutron flux degrades structural materials (neutron embrittlement) and activates reactor components. D-T fusion produces...
What is the physics behind Neutron Flux?
The intensity of neutron radiation passing through a given area per unit time, typically measured in neutrons per square centimeter per second (n/cm²/s). In fusion reactors, neutron flux is a critical design parameter: high neutron flux degrades structural materials (neutron embrittlement) and activates reactor components. D-T fusion produces...
What primary source PDFs are available for Neutron Flux?
1 PDF document is available: "An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation". This study presents an integrated computational framework combining neutron-transport calculations (MCNP), material inventory burn-up modeling (FISPACT), and electronic-structure density...
What external sources document Neutron Flux?
Neutron Flux is documented by 4 external sources, including 1 Encyclopedia Article, 1 Government Reference (U.S. Nuclear Regulatory Commission), and 1 Journal Article (Nuclear Fusion, IOPscience). Notable references include "Neutron flux - Wikipedia", "Neutron flux - NRC Glossary", and "An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation".
What is the current status of Neutron Flux?
The intensity of neutron radiation passing through a given area per unit time, typically measured in neutrons per square centimeter per second (n/cm²/s). In fusion reactors, neutron flux is a critical design parameter: high neutron flux degrades...
How does Neutron Flux relate to compact fusion research?
Overview The intensity of neutron radiation passing through a given area per unit time, typically measured in neutrons per square centimeter per second (n/cm²/s). In fusion reactors, neutron flux is a critical design parameter: high neutron flux degrades structural materials (neutron...
What documents should I read to learn more about Neutron Flux?
To learn more about Neutron Flux, review the 4 primary sources, 1 PDF document, and related research finding linked in the source documents section of this dossier.

External_References 5 REFS

/pdfs/DATRA-2026-Report.pdf#page=10 ref
/pdfs/DATRA-2026-Report.pdf#page=17 ref
/pdfs/DATRA-2026-Report.pdf#page=18 ref
/pdfs/FPA12_Wurden_LANL.pdf#page=28 ref
/pdfs/US20110142185A1.pdf#page=20 ref

Citations 1

  1. [1] (2012) — EURATOM/CCFE Fusion Association, Culham Centre for Fusion Energy

Verified_Primary_Sources 4 SOURCES

secondary wikipedia.org Encyclopedia Article
Neutron flux - Wikipedia
Verifies: Neutron flux is the total distance travelled by all free neutrons per unit time and volume; Measured in cm^-2 s^-1 (neutrons per square centimeter per second); Neutron flux is the primary quantity measured to control reactions in nuclear reactors
External Link ↗
primary nrc.gov Government Reference (U.S. Nuclear Regulatory Commission)
Neutron flux - NRC Glossary
Verifies: Neutron flux is a measure of the intensity of neutron radiation; Calculated as neutron density (n) multiplied by neutron velocity (v); Measured in neutrons/cm^2/sec
External Link ↗
primary iter.org Journal Article (Nuclear Fusion, IOPscience)
An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation
Verifies: D-T fusion produces 14.1 MeV neutrons; High-energy neutron fluxes have significant life-limiting impact on reactor components; Neutrons cause atomic displacements leading to hardening, embrittlement, and irradiation creep
External Link ↗
primary iopscience.iop.org Journal Article (Nuclear Fusion, vol. 52, no. 8, 2012)
An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation
Verifies: High-energy high-intensity neutron fluxes from fusion plasma have life-limiting impact on reactor components; Neutrons initiate nuclear reactions leading to transmutation and gas production causing swelling and embrittlement
External Link ↗
ID: glossary:neutron-flux
Type: concept
Region: glossary
Last updated: Research database snapshot