ANTECH
Neutron Active Crate Counter - Differential Die Away
nACC - Series 5400
Benefits
· Generic active crate counter tailored for neutron
counting of a variety of waste crates including
B25 boxes and the Standard Waste Box (SWB).
· Capable of both 'active' operation for the meas-
urement of fissile nuclides combined with a con-
ventional 'passive' mode capability for the meas-
urement of the fertile nuclides, principally 240Pu
giving complete flexibility for the measurement
of Pu and U in waste.
· Can be placed in a building or operated from a
remote location within a mobile ISO container.
· Measurement based on the differential die away
(DDT or DDA) principle using thermalized neu-
trons from a D-T generator to create induced fis-
sions in fissile material present in the waste.
· The system can be confirmed with HPGe gamma
ray based Pu isotopic ratio measurement sta-
tion--provides complete assay result.
·  In a non-moderating, non-absorbing (metallic)
waste matrix the nACC Series 5400 is capable of
achieving the USA TRU limit of 3700 Bq/g for
the measurement of uranium and plutonium.
Features
Robust construction avoiding 'high-Z' materials for reducing interfering neutron
·
background. Measurement chamber is lined with graphite producing a long neutron
die away time
·
Semi-automatic crate or box loading capability
·
Fitted with an MF Physics neutron generator of proven high reliability.
·
Typically, 24 fast neutron detector packages (4 in each of the two sides, the top and
bottom and the two ends), each containing 4 x 3He tubes (4 atmospheres fill pres-
sure).
·
Long die-away time (>1ms) and high neutron detection efficiency provide enhanced
sensitivity
·
The nuclear counting electronics includes a state-of-the-art multi-channel scaler for
active mode operation combined with a time correlation analyser (TCA) for passive
mode operation.
·
The counter is constructed for ease of maintenance, in particular for the replacement
of 3He tubes, leading to enhanced system reliability.
·
The counter can operate in conventional active totals neutron mode or in passive
coincidence counting mode, the latter where sufficient quantity of plutonium is
present in the waste.
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