6941

Uranium-235 ionization chamber designed for thermal-neutron flux measurement. Neutron-induced fission in the uranium-sensitive material produces ionization signals suitable for monitoring thermal-neutron intensity in nuclear instrumentation systems.

Directly heatedCold cathodeCommon cathodeDissimilarSpecialized

Sections: 1
Base: -
Socket code: -
Base pins: -
Nominal heater: 0 V / 0 mA

Description

Uranium-235 ionization chamber for thermal-neutron flux measurement; source also covers 6941.

General specifications

Tube and section characteristics

Properties common to every published source and operating point.

Heater and base

Base: -
Socket code: -
Base pins: -
Nominal heater voltage: 0 V
Nominal heater current: 0 mA
Parallel heater voltage: -
Parallel heater current: -
Series capable: No

Terminal pinout

Electrical assignments shared by every tube using this base designation.

No verified pinout is recorded for this base designation.

Section ratings

1 physical section, each with unique specifications.

Section 1

IonizationChamber

X-ray radiationInterelectrode capacitances

Max plate voltage: 1000 V

Published electrical limits and characteristics promoted from the approved source. Values without an applicable promoted column are retained in TUBE_SECTION_PARAMETER.

Source-dependent data

Operating conditions by source

Each block preserves the test conditions and published values from one reference. Values from different sources are intentionally kept separate.

Data set 01

1947 Westinghouse

Published operating points and test conditions from this source.

SECTION 1

IonizationChamber

Characteristic

NeutronSensitivity
2.6e-12 A per neutron/cm2/s
OperatingVoltageMinimum
200 V