ML23174A109
| ML23174A109 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 06/30/2023 |
| From: | Mirion Technologies Corp |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WL-6376A | |
| Download: ML23174A109 (6) | |
Text
Fission Counter Chamber MIRION Dual-Range TECHNOLOGIES Sensing Systems Division 1.4 to 1.4 x 105 nv Counter Range 6 x 105 to 1.4 X 1010 nv Chamber Range 300°F (1500C) Operation 0.7 cps/nv Counter Sensitivity 1.4 x 10-13 Alnv Chamber Sensitivity Meets MIL-S-901 & MIL-STD-167 (Typ 1)
Tube Number: WL-6376A Application The WL-6376A fission chamber is designed to detect thermal neutrons in the range of 1.4 to 1.4 x 105 neutrons!cm2!second when operate as a counter and in the range of 6 x 105 to 1.4 X IOlD neutronslcrn2!second when operated as a chamber. The detector is extremely ruggjd in construction, meeting MIL-S-901 for shock and MIL-STD-167 (Type I) for vibration, and may be operated in any position at temperatur sup to 300°F (l50°C).
The WL-6376A is constructed of aluminum, with high purity alumina ceramic insulators throughout, including those used in the typ~ HN connector. In typical operation as a fission counter the WL-6376A has a thermal neutron sensitivity of approximately 0.7 counts!neutro /cm2 throughout a wide range of applied voltage. When connected for service as an ionization chamber, the thermal neutron sensitivi is approximately 1.4 x 10.13 amperes/neutron/cmvsecond with a gamma sensitivity of approximately 4.2 x 10*1l ampereslRlhour.
Mechanical Diameter (50.8 mm) 2.00 Inches Overall Length (292 mrn) 11.5 Inches Approximate Sensitive Length (152) 6 Inches Net Weight (794 grams) 1.75 Pounds Shipping Weight (5.4 kg) 12 Pounds Materials Outer Case : Aluminum Electrodes Aluminum Insulation A1203 Sensitive Material:
Amount ofU235 in U308 >90 %
Thickness ~ 2.0 m'g/crn2 Gas Fill Ar-N Gas Pressure 76 crn-Hg Impedance Resistance (minimum) (At Max. Temp.) 10.9 Ohms Capacitance 150 pF Maximum Ratings Voltage between Electrodes 1000 Volts Temperature (lSO°C) 300 OF External Pressure (Note 1) (7.0 kglcm2)100 psig Thermal Neutron Flux .3 x 10lDnv Typical Operation as a Connter (at approx. 25°C)
Operating Voltage 300 Volts Operating Voltage Plateau 200-800 Volts Thermal Neutron Flux Range 1.4 to 1.4 x 105 Volts Sensitivity (Note2) 0.7 nv Output Pulse Characteristics:
Amplitude (unloaded) 2 x 10-4Volts Inherent Rise Time (average) 2 x 10.7 Seconds
Tube Number: WL-6376A Page 2 Typical Operation as a Chamber (at approx. 25°C)
Operating Voltage (Note 3) , 300-1000 Volts Thermal Neutron Flux Range (Note 4) 6 xlO'5 to 1.4 x 1010Nv Thermal Neutron Sensitivity 1.4 x 10-13Alnv Gamma Sensitivity 4.2 x 10-11AlR/Hr Alpha Background Current 1.6 x IO-8A Notes
- 1. The pressurizing atmosphere must be dry and non-corrosive.
- 2. The sensitivity given is with the alpha background counting rate of the naturally radioactive uranium adjusted to 5 counts/second. By varying the pulse height selector on the associated circuitry, or by use of high resolution circuitry, other sensitivities are available.
- 3. The minimum voltage required for saturation is dependent upon the incident neutron flux level.
4, The lower limit of operating range is determined by an inherent alpha background current.
Document information is subject to change without notice and contains proprietary information which may not be accurate.
Data Sheets - Marketing\6376A Scanned 07113/09
Uncompensated Ionization Chambers I 3" Diameter - Guard Ring TECHNOLOGIES Tube Maximum Sensitivity Sensing Systems Division Type Temp. of A/nv
---.;1>--==-WL-6937 A 300 7.6 x 10.14 WL-7606 575 7.6 X 10-14 WL-8075 300 7.6 X 10.14 WL-23272 300 3.3 X 10*]3
. Application This group of uncompensated ionization chambers is designed to operate in a thermal neutron to gamma flux ration of 104 IlV to IRzbr or greater, These Chal1E~
feature guard-ling construction to minimize the effect of interelectrode leakage currents, They are extremely rugged and may be operated in any position up to eir rated temperature, The materials used in construction of file detector, including those of the type HN connectors, have been selected for low activation prope ies, This reduces the magnitude and duration of act ivation currents and facilitates handling after exposure to high neutron fluxes.
-It Mechanical Units WL-6937A WL-7606 WL-8075 WL-2327 O.D., Nominal . Inches 3.00 3.00 3.00 3.00 Length, Nominal . Inches 13.62 13.62 13.62 21.50 Sensitive Length, Nominal . Inches 7.0 7.0 7.0 14.0 Net Weight . Pounds 2.5 2.5 2.5 3.75 Shipping Weight , . Pounds 10.0 10.0 10.0 11.5 Materials Outer Case .................................................. .; .................. Aluminum Aluminum Aluminum Aluminum Electrodes. ....................................................................... Aluminum Aluminum Aluminum Aluminum Insulation ......................................................................... AhO, AhO) AhO) AhO)
Neutron Sensitive Material:
Content ....................................................................... Boron (Bill) Boron (B'") Boron (B'o) BIOF)
Thickness ................................................................... mg/cm2 0.8 0.8 0.8 Gas Fill ....................................*....................................... Ar-Nz Ar-N2 AI'-N2 81°F3 Impedance Resistance, Minimum:
Signal Electrode to Case ............................................ Ohms 1011 1011 1011 1011 H.V. Electrode to Case .............................................. Ohms 1011 1011 10-" 1011 -1, Capacitance (Notel):
Signal Electrode to Case ........................................... pF 170 170 170 180 H.V. Electrode to Case .............................................. pF 250 250 250 275 Maximum Ratings Voltage Between Electrodes: ......................................... Volts d.c, 1500 1500 1500 2500 Temperature ............................................................... OF 300 575 300 300 External Pressure (Note 2) ........................................ PSI 180 180 180 180 Thermal Neutron Flux .................................................... llV 2.5 x 10" 2.5 X ro 2.5 X io" 2.5 X 10" Gamma Flux ................................................................... Ribr [07 [07 107 107 Typical Operation Operating Voltage (Note 3) ........................................... Voltsd.c. 200-1000 200*1000 200-1000 200-2000 Saturation Characteristics .............................................. See Fig. 6 See Fig. 6 See Fig. 6 See Fig. 5 Thermal Neutron Flux:
Lower Limit ................................................................ nv 2.5 x 102 2.5 X 102 2.5 X 102 3.0 X 101 Upper Limit ................................................................. nv 5.0 x 1010 5.0x 10'" 5.0 X 1010 5.0" 109 Thermal Neutron Sensitivity:
Reactor (Note 4) ......................................................... Alnv 4.4 x 10.14 4.4 X 10.14 4.4 X 10.14 Source Box (Note 5) ................................................... Alnv 7.6 x 10.14 7.6 X 10.14 7.6 X 10"4 3.3 X 1O-t)
Gamma Sensitivity: (Note 6) ....................................... AlR/hr 4.0.x 10.11 4.0x 10.11 4.0 X 10 1.3 x ]0.1(1 Notes I. Capacitance is measured between an electrode and case with all other electrodes grounded 10 the case.
t
- 2. The pressurizing atmosphere mnst be dry and non-corrosive, 3'. The saturation voltage varies with CUITent level. See saturation characteristics for proper operating voltage.
- 4. The reactor sensitivity was determined experimentally. however perturbation effects may alter the effective neutron sensitivity.
- 5. The Thermal Neutron Sensitivity is determined in a Pu-Be source box. Reactor environments often produce significant flux perturbation which n . y alter the effective neutron sensitivity.
- 6. The gamma sensitivity is determined in a Co'" flux.
Uncompensated Ionization Chambers 3" Diameter - Guard Ring Page 2 Tube Maximum Sensitivity Type Temp. OF Alnv
~WL-6937A 300 7.6 x 10-14 WL-7606 575 7.6 X 10-14 WL-8075 300 7.6 X 10-14 WL-23272 300 3.3 X 10-13 WL-23272 WL-6937A WL-760a WL-8075 (2) HN Jack.
Mal *** 1It1 (21 HN ,Jocks MIL-\IG 59AIU Mole with Offllu}volcnl.
NIL-UC S9A/U or~uf'tCltJlt.
/' /
FIGURE 2 FIGURE 3 FIGURE 1 TYPICAL CONNECTION DIAGRAM WL*6937A RANGE CHART WL-7606 WL-B075 10'2 TYPICAL SATURATION CHARACTERISTICS 10'2 !mffittmtm !63A JO-3A FIGURE 4 -=
WL*23272 1)'P1CAL SATURATION CHARACTERIS11CS cr~E!l~~ttti~
3
[ 10-
~ I r;
i" IOIiA Wl:6937 A---'
!O-fIA WL-7606 1O-70~~~~~~~~~~~1~~~1~~
I Wl:23272 WI:B075 600 1200 1600 2400 3000 AppJlad VOIiIi d.c.. Applied Volls de, CC ..**.I2..'R A4 FIGURE 6 FIGURE 7 FIGURE 5 Document information is subject to change without notice and contains proprietary information which may not be accurate Scanned 07128/11 Data Sheets - Marketing\6937A 7606 8075 23272
Compensated Ionizafon MIRION Chamber TECHNOLOGIES WL-23084 Sensor and Control Division APPLICATION The WL-23084 Compensated Ion Chamber is designed to operate in a thermal neutron to gamma flux rat 0 of 500 nv to 1 Rlhr with 95% compensation. This chamber employs guard-ring construction to minimiz the effect of inter-electrode leakage current, permitting operation from 230 nv to a maximum of 5x1010 nv.1The chamber materials, including those of the type HN connectors, have been selected for their low activ tion properties. The use of such materials reduces the magnitude and duration of the activation currents;and facilitates handling of the chamber after it has been exposed to high neutron fluences. This chamb r is extremely rugged and may be operated in any position up to the rated temperature; however, operation i an end-on flux will shift the chamber's compensation characteristic and may alter its effective neutron sensitivi I
- MECHANICAL Outside Diameter (nominal) 3.16 Inches (79.4 mm)
Length (nominal) 19.17 Inches (486.9mm)
Sensitive Length (nominal) 14.0 Inches (355 em) {::S)HN JA(II;S Net Weight 5.7 Pounds (2.6 kg) H..I.T£W1TH HIL-:)ti59 A/U Shipping Weight......................................... 19.0 Pounds (9.6 kg) DR EQuiVAL~IIT, MATERIALS Outer Case ; . Aluminum Electrodes . Magnesium and Aluminum L
2.0 150.'1
- Insulation . Alumina Ceramic Neutron Sensitive Material Content B-10 Enriched Boron Thickness (Approx.) . 0.8mgicm2 Gas Filling . Nitrogen (with Helium Trace) 191 :19 SEHSIfI\1i (loSe. !;t..8 LEI"'GT" IMPEDANCE "
[3:)5.61 1712 .*.12 AP~RO;l;,
[1.50.1 !J.o]
Resistance, minimum (Note 1)
H.V Electrode to Case..... 1012Ohms Signal Electrode to Case 1013Ohms Compensating Electrode to Case 1012 Ohms es.re ~ Of)
Approximate Capacitance (Note 2) 290 pF {aO . .3!J.5 Signal to Case H.V. to Case 330 pF Compensating Electrode to Case....... 182pF MAXIMUM RATINGS Voltage between Electrodes........................ 1500 Volts DC Temperature :............................. 400°F\205°C)
Thermal Neutron Flux 5 x 101 nv External Pressure (Note 3) 180 psig (12 kg/ern')
WL-23084 10-31-2007
Compensated Ionization Chamber WL-23084 Page 2 TYPICAL OPERATION Operating Voltage . 300 to 1500 Volts DC Compensating Voltage . -10 to -80 Volts DC Saturation Characteristics (Note 4) . See Figure 1 Thermal Neutron Flux Range 1.3 x 103 to 5.0 X 1010 nv Thermal Neutron Sensitivity Source Box (Note 5) 7.6 x 10"14Alnv Reactor (Note 6) 4.4 X 1O~14 Alnv Gamma Sensitivity (Note 7)
Total Compensation 0 AlR/hr Uncompensated 2.3 x 10"11 AlRJHr NOTES
- 1. The detector is not designed for immersion in water. High humidity environments may degrade performance.
- 2. Capacitance is measured between an electrode and case with all other electrodes grounded to the case.
- 3. The pressurizing atmosphere must be dry and non-corrosive.
- 4. Saturation voltage varies with current level. See saturation characteristics for proper operating voltage.
I
- 5. Thermal neutron sensitivity is evaluated using an AmBe source.
Reactor environments often produce significant flux perturbation which may alter the effective sensitivity.
- 6. The reactor sensitivity was determined experimentally. However, perturbation effects and reactor spectrum may alter the effective neutron sensitivity.
- 7. The gamma response is determined using a Co60 source.
WL-23084 10-31-2007