224
M. Yamanaka
Table 8.3 Comparison between measured and calculated (MCNP6.1) results of excess reactivity
and control rod worth in EE1 and E3 cores (Ref. [1])
(a) EE1
Reactivity
Exp. [pcm]
Cal. [pcm] (C/E value)
JENDL-4.0
ENDF/B-VII.0
Excess
210 ± 6
198 ± 18 (0.94 ± 0.09)
196 ± 18 (0.93 ± 0.09)
C1 rod
838 ± 11
857 ± 18 (1.02 ± 0.02)
843 ± 18 (1.01 ± 0.02)
C2 rod
144 ± 3
134 ± 18 (0.93 ± 0.13)
135 ± 18 (0.94 ± 0.13)
C3 rod
521 ± 8
500 ± 18 (0.96 ± 0.04)
491 ± 18 (0.94 ± 0.04)
(b) E3
Reactivity
Exp. [pcm]
Cal. [pcm] (C/E value)
JENDL-4.0
ENDF/B-VII.0
Excess
264 ± 2
246 ± 16 (0.93 ± 0.06)
241 ± 16 (0.91 ± 0.06)
C1 rod
551 ± 6
526 ± 16 (0.95 ± 0.03)
536 ± 16 (0.97 ± 0.03)
C2 rod
429 ± 4
400 ± 16 (0.93 ± 0.04)
388 ± 16 (0.90 ± 0.04)
C3 rod
329 ± 4
314 ± 16 (0.95 ± 0.05)
315 ± 16 (0.96 ± 0.05)
Table 8.4 Numerical results by MCNP6.1 eigenvalue calculations in critical state (Ref. [1])
EE1
E3
JENDL-4.0
ENDF/B-VII.0
JENDL-4.0
ENDF/B-VII.0
1.00246 ± 0.00009
1.00461 ± 0.00009
1.00443 ± 0.00008
1.00578 ± 0.00008
of about 250 pcm, and with ENDF/B-VII.0 a value about 460 pcm (Table 8.4).
Similarly, in E3 core, the value with JENDL-4.0 was small, about 440 pcm, compared
with that with ENDF/B-VII.0, about 580 pcm. From the analyses of eigenvalue bias,
a significant index of the accuracy of experimental analyses was acquired by MCNP
calculations in EE1 and E3 cores at KUCA; also, as in previous studies [12, 19],
JENDL-4.0 was considered reliable as a reference nuclear data library in a series of
sensitivity and uncertainty analyses of excess reactivity and control rod worth in the
KUCA A core.
The numerical values of k eff in excess reactivity and control rod worth shown in
Eqs. (8.5) and (8.6), respectively, were deduced, for a clean core (withdrawal of all
control and safety rods) and a subcritical core (control rod insertion) in super-critical
and subcritical states, respectively, through the results of diffusion-based eigenvalue
calculations (CITATION) in the 107-energy-group and x-y-z dimensions (3-D) with
JENDL-4.0. Also, on the basis of accuracy of experimental analyses by CITATION
(Table 8.5), sensitivity analyses of k eff in excess reactivity and control rod worth were
notably conducted by diffusion-based calculations (SAGEP).
M. Yamanaka
Table 8.3 Comparison between measured and calculated (MCNP6.1) results of excess reactivity
and control rod worth in EE1 and E3 cores (Ref. [1])
(a) EE1
Reactivity
Exp. [pcm]
Cal. [pcm] (C/E value)
JENDL-4.0
ENDF/B-VII.0
Excess
210 ± 6
198 ± 18 (0.94 ± 0.09)
196 ± 18 (0.93 ± 0.09)
C1 rod
838 ± 11
857 ± 18 (1.02 ± 0.02)
843 ± 18 (1.01 ± 0.02)
C2 rod
144 ± 3
134 ± 18 (0.93 ± 0.13)
135 ± 18 (0.94 ± 0.13)
C3 rod
521 ± 8
500 ± 18 (0.96 ± 0.04)
491 ± 18 (0.94 ± 0.04)
(b) E3
Reactivity
Exp. [pcm]
Cal. [pcm] (C/E value)
JENDL-4.0
ENDF/B-VII.0
Excess
264 ± 2
246 ± 16 (0.93 ± 0.06)
241 ± 16 (0.91 ± 0.06)
C1 rod
551 ± 6
526 ± 16 (0.95 ± 0.03)
536 ± 16 (0.97 ± 0.03)
C2 rod
429 ± 4
400 ± 16 (0.93 ± 0.04)
388 ± 16 (0.90 ± 0.04)
C3 rod
329 ± 4
314 ± 16 (0.95 ± 0.05)
315 ± 16 (0.96 ± 0.05)
Table 8.4 Numerical results by MCNP6.1 eigenvalue calculations in critical state (Ref. [1])
EE1
E3
JENDL-4.0
ENDF/B-VII.0
JENDL-4.0
ENDF/B-VII.0
1.00246 ± 0.00009
1.00461 ± 0.00009
1.00443 ± 0.00008
1.00578 ± 0.00008
of about 250 pcm, and with ENDF/B-VII.0 a value about 460 pcm (Table 8.4).
Similarly, in E3 core, the value with JENDL-4.0 was small, about 440 pcm, compared
with that with ENDF/B-VII.0, about 580 pcm. From the analyses of eigenvalue bias,
a significant index of the accuracy of experimental analyses was acquired by MCNP
calculations in EE1 and E3 cores at KUCA; also, as in previous studies [12, 19],
JENDL-4.0 was considered reliable as a reference nuclear data library in a series of
sensitivity and uncertainty analyses of excess reactivity and control rod worth in the
KUCA A core.
The numerical values of k eff in excess reactivity and control rod worth shown in
Eqs. (8.5) and (8.6), respectively, were deduced, for a clean core (withdrawal of all
control and safety rods) and a subcritical core (control rod insertion) in super-critical
and subcritical states, respectively, through the results of diffusion-based eigenvalue
calculations (CITATION) in the 107-energy-group and x-y-z dimensions (3-D) with
JENDL-4.0. Also, on the basis of accuracy of experimental analyses by CITATION
(Table 8.5), sensitivity analyses of k eff in excess reactivity and control rod worth were
notably conducted by diffusion-based calculations (SAGEP).