The development program utilized various test sites for evaluation of the prototype hardware. These test sites are described as. follows:

a. NEPS — Building W. Neutron Source Site ‘ •

This facility contains a small, neutron source from which a neutron flux of approx — ■ 4

imately 1. 5 x 10 nv is available. This flux was used to determine initial operability of the counting electronics hardware. In addition, measurements of counting system noise and in-core detector and cable temperature effects were conducted at this site.

b. Vallecitos — Cobalt-60 Facility

• , C —

The effect of gamma flux, up to a maximum value of 3 x 10° R/h. on the counting

and Campbell systems was investigated under ambient temperature conditions. .

Additional tests were performed at various gamma flux levels for both systems.

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using a small neutron source of approximately 3 x 10 nv in close proximity to the detectors. .

c. Vallecitos — Nuclear Test. Reactor (NTR)

This facility was used to determine counting system range, linearity and approximate

system response during mechanical withdrawal movements of the detector, and

linearity of the Campbell system over the available flux range at NTR. This reactor ■ 4 ■ .

is easily controlled from a source level flux of approximately 10 nv to a maximum flux

of 6‘. 6i x 10s^ nv. The maximum’ gamma dose rate at full’ power is approximately

2 x 10 R/h for this reactor. A number of response measurements were also made

for both counting, and Campbell systems as a function of time following a reactor scram.

d. Vallecitos — General Electric Test Reactor (GETR)

A measurement of the Campbell system linearity up to a peak flux of approximately 14

10 nv was made in the Z trail cable. Campbell and counting system performances as a function of time following shutdown were recorded in order to make the sensitivity determination. .

SECTION II