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NRL Irradiation Facility Neutron Fluxes and Neutron & Gamma Dose Rates

NRL Irradiation Facility Neutron Fluxes and Neutron & Gamma Dose Rates
Facility Total Neutron Flux (n cm-2 s-1) Percent Thermal (%) Thermal Neutron Flux (n cm-2 s-1) epi-Cd Neutron Flux (n cm-2 s-1) 1.0 MeV Equivalent Neutron Flux (n cm-2 s-1) Neutron Dose Rate in Si (rad-Si/hr) Gamma Dose Rate in Si (rad-Si/hr)
1.3" CIF 2.7E13* 60 1.6E13* 1.1E13* 5.6E12 (Si)^, 6.0E12 (GaAs)^ 1.6E06# 8.7E07§
2.4" AIF 1.1E13** 54 6.0E12** 5.2E12** 2.3E12 (Si)^, 2.5E12 (GaAs)^ 6.9E05# 3.8E07§
Pneumatic Transport System (PTS) / Rabbit 3.4E12^^ 69 2.3E12^^ 1.1E12^^ 5.5E11 (Si)^, 6.0E11 (GaAs)^ 1.6E05# not measured
6.5" External Dry Tube 1.9E12## 75 1.4E12## 4.9E11## 2.7E11 (Si)^, 3.0E11 (GaAs)^ 8.5E04# 7.6E06§
9.5" External Dry Tube
(Flux Box Evacuated)
1.1E12§§ 74 8.0E11§§ 2.9E11§§ 1.6E11 (Si)^, 1.8E11 (GaAs)^ 4.8E04# 4.4E06§
Thermal Column
G7, core end, stringer open
not measured not measured 2.7E11*** not measured not calculated not calculated not measured
Thermal External Beam Line Facility (TBF) not measured not measured 3.4E06^^^ not measured not calculated not calculated not measured
Fast External Beam Line Facility (FBF) – No Thermal Filter – Gamma Shutter Open 2.3E07### 36 0.8E07### 1.5E07### not calculated not calculated not measured
Fast External Beam Line Facility (FBF) – No Thermal Filter - Gamma Shutter Closed 2.9E05§§§ 9 0.3E05§§§ 2.6E05§§§ not calculated not calculated not measured

Note: All values are listed at a reactor power of 450 kW

NRL Irradiation Facility Dimensions
Facility Inner Dimension
Central Irradiation Facility (CIF) 1.3" diameter
Auxiliary Irradiation Facility (AIF) 2.4" diameter
Pneumatic Transport System (PTS) / Rabbit 1.1" diameter = mouth of the polyethylene sample bottles used in the PTS
6.5" Movable Dry Tube 6.6" diameter
9.5" Movable Dry Tube 9.5" diameter
Thermal Column 4" x 4" Square / Stringer
Thermal External Beam Line Facility (TBF) ~30 mm diameter
Fast External Beam Line Facility (FBF) ~30 mm diameter

* NRL memo 2020-15 Rev 01, "CIF Neutron Spectrum Measurement"

^ NRL memo 2013-12 Rev 07, "1.0-MeV-Equivalent Flux Calculations in Si and GaAs"

# NRL memo 2021-04, "Facility Characterization - Neutron Dose Rate in Silicon"

§ NRL memo 2016-17 Rev 03, "Gamma Dose Rates of Reactor Facilities"

** NRL memo 2020-16 Rev 01, "AIF Neutron Spectrum Measurement"

^^ NRL memo 2020-18 Rev 01, "Rabbit Neutron Spectrum Measurement"

## NRL memo 2020-19 Rev 01, "6.5-inch External Dry Tube Neutron Spectrum Measurement"

§§ NRL memo 2020-22, "9.5-inch External Dry Tube (Flux Box Evacuated) Neutron Spectrum Measurement"

*** NRL memo 2021-14, "Thermal Flux Measurements within Thermal Column Sample Holder"

^^^ NRL memo 2020-20, "Thermal Beam Facility Flux Measurements"

### NRL memo 2021-12 Rev. 02, "Fast Beam Facility (No Thermal Filter) Neutron Spectrum Measurement"

§§§ NRL memo 2022-14, "Fast Beam Facility Shutter Closed (No Thermal Filter) Neutron Spectrum Measurement"

Tables are available in PDF format

These tables can also be downloaded as a PDF.

 

Experiment rig being lowered into OSURR large external dry tube