Jt. Mihalczo et al., THE CENTRAL VOID REACTIVITY IN THE OAK-RIDGE-NATIONAL-LABORATORY ENRICHED URANIUM(93.2) METAL SPHERE, Nuclear science and engineering, 130(1), 1998, pp. 153-163
The reactivity worth of a central void region in the Oak Ridge Nationa
l Laboratory (ORNL) unmoderated and unreflected uranium (93.20 wt% U-2
35) metal sphere was obtained by replacement measurements in a small (
0.460-cm-diam) central spherical region in this 3.4420-in.-radius sphe
re. The measured central void region worth was 9.165 +/- 0.023 c using
the delayed neutron parameters of Keepin, Wimett, and Zeigler to obta
in the reactivity from the measured stable reactor periods. This value
is slightly larger than measurements for GODIVA I with larger cylindr
ical samples of uranium (93.70 wt% U-235) in, the center: 135.50 +/- 0
.12 c/mol for GODIVA I and 138.05 +/- 0.34 c/mol for the ORNL sphere m
easurements. The difference could be due to sample size effect. The ce
ntral worth was also calculated by neutron transport theory methods to
be 6.02 +/- 0.01 x 10(-4) Delta k. The measured and calculated values
are related by the effective delayed neutron fraction. The value of t
he effective delayed neutron fraction obtained in this way from the OR
NL sphere is 0.00657 +/- 0.00002, which is in excellent agreement with
that obtained from GODIVA I measurements, where the effective delayed
neutron fraction was determined as the increment between delayed and
prompt criticality and was 0.0066. From these ORNL measurements, using
the delayed neutron parameters of ENDF-B/VI to obtain the reactivity
from the stable reactor period measurements, the central void worth is
7.984 +/- 0.021 c, and the inferred effective delayed neutron fractio
n is 0.00754. These values are 14.2% higher than those obtained from u
se of the Keepin, Wimett, and Zeigler delayed neutron data and produce
a value of effective delayed neutron fraction in disagreement with GO
DIVA I measurements, thus questioning the usefulness of the six-group
delayed neutron parameters (fast fission) of uranium from ENDF-B/VI fo
r obtaining the reactivity from the measured reactor period using the
Inhour equation.