Neutron production by neutral beam sources Page: 3 of 5
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Directional collimstfoo was not need to prevent
one detector froe re* pood In* to the source auoclit*d
with the other detectors. However, corrections s*
high S3 112 have been made to the ncutiallxer neotroa
data to remove the cootributios froei the calorimeter.
Starting with net trials that have not onc ex-
po aed to deuterli* beams, we aae « balling la matron
production aa the bomberrant continues. Zvnatemlly
a plateau la approached as the dlfission cf deterecs
out of the lattractive layer cornea Into agulllbrlw
with the Implantation rate. An cradle la given Is
Fig. 4 for 120-kaV, 8-A.aod 42-keT, 2-A btM slopping
Integrated beam porticles (*6.24*10*)
Fig. 4. Neutron-production buildup in a copper target
as a function of bean fluence.
In the copper calorimeter. The BF^ detectors were
used to determine when equilibrium neutron production
was attained- The aoderated lndlim -detectors were
then used to determine the neutron production from a
Neutron yields given In Table I are normalized
to 1-A on the calorimeter for continuous (non-pulsed)
beams. A point source 1b assumed for the calorimeter.
Attenuation of neutrons by the vacuum wall and copper
calorimeter is assumed to be offset by a 20Z contri-
bution by scattering into the detector from the floor,
walls and equipment. The neutralizer colim Is con-
sidered to be a 2m uniform line source.
Three loo species are produced in the plasma source,
D+, fit and D"!\ which, after acceleration, result In
full-, half-, and one-third energy conponents. Table
II. An estimate of the fractional, neutron yields of
Table 1. Nuiared Imitmtmwm neutral yield p-:r
Itn of dMCeroms (D* + 0°>
mrnm tielo (s/scc-a)
1.4 « 10*
4.0 . 10*
1.1 « io"
2.4 « lO11
4.7 » 10U
7.7 » 10*
2.4 » 109
4.1 » 109
8.4 . 109
1.2 " 1010
atomic (fmll energy; and molecular (1/2 emd i/3 energy)
coapooemte have haem made (aee Table II) which are
bailed on prior experimental kmmledge of the fractional
power yields of the beam species, end the Integrated
reaction cross sections ns given by Kin.4
The ralculatlonal method used Is shown below.
Reutrna yield, Q, for en atomic beam la given by:
A - <31. I 0 [E(a)]dx, neutrona/secant)
where d *0
C - saturaied deuterium density (unmed
■ml form throughout 2)
- number of demterlum beam particles/sec
B ■ denteron range
0 ■ d-d resetioo cross section at energy E at
ft is assumed that the talented saturated deu-
tcrlia density in the calorimeter Is essentially
constant over the. range of the Incident demerits beam.
Justification for this assumption stems from the work
of Bartle et si.* mad by Bilton et al.6
The integrated reaction cross sections of Klm\
shown in Fig. 5,«r* used because of the strong depen-
dence of cross section on the energy of c*»e incident
beam particles which are continuously degraded In energy
tntll th^y are completely stofped within the target.
From JL Kim,
Nuclear Uittr. AMcfh.
•45 11977) 9-17
Beom energy (keV'
1 regrated reaction cross sections frc„ Ref. 4.
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Berkner, K.H.; Massoletti, D.J.; McCaslin, J.B.; Pyle, R.V. & Ruby, L. Neutron production by neutral beam sources, article, November 1, 1979; Berkeley, California. (https://digital.library.unt.edu/ark:/67531/metadc1084880/m1/3/: accessed April 20, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.