WPEC SG 21: Assessment of Neutron Cross-Section Evaluations for the Bulk
of Fission Products

**Sr-89**

Reviewed by Shen Qingbiao CIAE, February, 2004

**1. Files**

***ENDF/B-VI***: Evaluation was made in 1974. It was converted to
ENDF/B-VI in 1990.

***JENDL-3.2***: Evaluation was made for JENDL-3. in 1990. It was
converted to JENDL-3.2 in 1994.

***JEF-2.2***: ENDF/B-V was adopted in 1982. The charged particle
production cross sections were added from REAC-ECN-4 library in 1989.
The data were compiled in 1992.

***CENDL-3***: Evaluation was performed in 1999. The re-evaluation was
compiled in 2001.

Figs: <http://www.nndc.bnl.gov/sg21/fp21/index.html>

**2. Thermal and resonance region**

\(1\) Resolved resonance parameters

***ENDF/B-VI***

No resolved resonance parameters are given.

***JENDL-3.2***

No resolved resonance parameters are given.

***JEF-2.2***

No resolved resonance parameters are given.

***CENDL-3***

No resolved resonance parameters are given.

\(2\) Unresolved resonance parameters

***ENDF/B-VI***

No unresolved resonance parameters are given.

***JENDL-3.2*** (1.4 - 100 keV)

The neutron strength function S0 and S2 were calculated with optical
model code CASTHY \[Ig75\], and S1 was based on the systematics of
Mughabghab et al. \[Mu81\].

***JEF-2.2***

No unresolved resonance parameters are given.

***CENDL-3*** (1.4 -- 100 keV)

JENDL-3.2 was adopted.

\(3\) Recommendation/conclusion for resonance region

***JENDL-3.2*** (***CENDL-3***) is recommended.

**3. Fast neutron region**

\(1\) Methodology

***ENDF/B-VI***

Theoretical calculation was widely used.

The isotropic distributions were given.

The evaporation energy spectra were given

***JENDL-3.2***

The total, elastic and inelastic scattering, and capture cross sections
were calculated with the spherical optical model and statistical model
code CASTHY. No direct inelastic was considered. Other reaction cross
sections were calculated with a preequilibrium and multi-step
evaporation code PEGASUS. Sum of the threshold reaction cross sections
were considered as a competing reaction cross sections in the CASTHY
calculation.

Angular distributions of elastic and inelastic scattering were
calculated with CASTHY code. Isotropic distributions were assumed to the
other reactions.

The energy distributions were calculated with PEGUSUS code.

***JEF-2.2***

ENDF/B-V data were adopted. The charged particle production cross
sections were added from REAC-ECN-4 library.

***CENDL-3***

Calculated with SUNF code. The optical model parameters were determined
with APOM code. The direct inelastic scattering data were calculated by
DWUCK4 code.

Angular and energy distributions of neutrons were also calculated with
SUNF code.

\(2\) Total cross section (MT=1)

The total cross sections of ***CENDL-3*** pass through the experimental
data at 14.2 MeV of Sr-88, and the other libraries are higher than the
experimental data of Sr-88.(see next Fig.)

![](media/image1.png){width="6.490277777777778in"
height="4.8381944444444445in"}

\(3\) Capture cross section (MT=102)

The value and shape of curve of cross sections are reasonable and
acceptable for ***CENDL-3*** and ***JENDL-3.2***. The shapes of curve of
cross sections are not good for ***ENDF/B-VI*** and ***JEF-2.2.***

\(4\) Elastic scattering cross section (MT=2)

This cross section was obtained as (total cross section) -- (sum of
partial cross sections) in the all

libraries.

\(5\) Inelastic scattering cross section (MT=4, 51 -- 91)

Excited levels considered in the files.

> ENDF/B-VI 12 levels up to 3.74 MeV
>
> JENDL-3.2 11 levels up to 2.671 MeV
>
> JEF-2.2 12 levels up to 3.74 MeV
>
> CENDL-3 17 levels up to 3.1389 MeV

The shape and value of curve of total inelastic scattering cross
sections of ***CENDL-3*** and ***JENDL-3.2*** are reasonable and
acceptable. But the values of curve of total inelastic scattering cross
sections of ***CENDL-3***

are closed to the experimental data of Y-89 than ***JENDL-3.2*** (see
next Fig.). And the direct inelastic scattering contribution is
considered for ***CENDL-3*** only. The shape of curve of total inelastic
scattering cross sections of ***ENDF/B-VI*** and ***JEF-2.2*** is wrong
since no (n,2n) cross sections are given.

![](media/image2.png){width="6.490277777777778in"
height="4.8381944444444445in"}

\(6\) (n,2n) reaction cross section (MT=16)

The shape and value of (n,2n) cross sections of ***CENDL-3*** and
***JENDL-3.2*** are very closed each other. No this file for
***ENDF/B-VI*** and ***JEF-2.2***.

\(7\) (n,p) reaction cross section (MT=103)

The shape and value of (n,p) cross sections of ***CENDL-3*** and
***JENDL-3.2*** are very closed each other (see next Fig.). They are
closed and lower the experimental data of Sr-88. Because Z/N=0.76 and
0.745 for Sr-88 and Sr-89, it is reasonable that the (n,p) cross
sections of Sr-89 is lower than Sr-88. The (n,p) cross sections of
***JEF-2.2*** is too low.

![](media/image3.png){width="6.490277777777778in"
height="5.5784722222222225in"}

\(8\) (n,) reaction cross section (MT=107)

The difference of the (n,) reaction cross sections between Sr-88 and
Sr-89 for ***JENDL-3.2*** is too large and they are closed each other
for ***CENDL-3*** (see next Fig.).

![](media/image4.png){width="6.490277777777778in"
height="4.636805555555555in"}

The shape and value of (n,) cross sections of ***CENDL-3*** are closed
to and lower than the experimental data of Y-89 (see next Fig.). Because
Z/N=0.78 and 0.745 for Y-89 and Sr-89, it is reasonable that the (n,)
cross sections of Sr-89 is lower than Y-89. The (n,) cross sections of
***JENDL-3.2*** is too low.

![](media/image5.png){width="6.490277777777778in"
height="4.8381944444444445in"}

The shape and value of (n,) cross sections of ***CENDL-3*** are closed
to and lower than the experimental data of Zr-92 (see next Fig.).
Because Z/N=0.769 and 0.745 for Zr-92 and Sr-89, it is reasonable that
the (n,) cross sections of Sr-89 is lower than Zr-92. The (n,) cross
sections of ***JENDL-3.2*** is too low. The (n,) cross sections of
***JEF-2.2*** is very low.

![](media/image6.png){width="6.490277777777778in"
height="4.636805555555555in"}

\(9\) Other reactions

The following other reaction cross sections are given in the files.

> JENDL-3.2 (n,3n), (n,n), (n,np), (n,nd), (n,d), (n,t)
>
> CENDL-3 (n,3n), (n,n), (n,np), (n,d), (n,t), (n,He-3)
>
> JEF-2.2 (n,d), (n,t), (n,He-3),(n,2p)
>
> ENDF/B-VI No

\(10\) Recommendation/conclusions for fast neutron region

***CENDL-3*** is recommended.

**References**

\[Ig75\] IGARASI, S.: J. NUCL. SCI. TECHNOL., 12, 67, 1975.

\[Mu81\] Mughabghab S.F. et al.: "Neutron Cross Sections, Vol.1, Part
A," Academic Press (1981).

\[Ro57\] Roy L. and Roy J., J, CJP, 35, 1215, 1957.

Table 1. Summary for Resolved and Unresolved Resonance Region: Sr-89

\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\--

Library RRP URP Remarks

\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\--

ENDF/B-VI No RRP No URP

JENDL-3.2 No RRP 1.4\--100 keV

JEF-2.2 No RRP No URP

CENDL-3 No RRP 1.4\--100 keV taken from JENDL-3.2

\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\--

Table 2. Thermal Cross Sections and Resonance Integral: Sr-89

\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\--

Library/Experiment Total Elastic Capture Res.Integ.

\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\-\--

ENDF/B-VI 4.064 3.644 0.42 0.527

JENDL-3.2 6.12 5.70 0.42 0.414

JEF-2.2 4.064 3.644 0.42 0.527

CENDL-3 6.12 5.70 0.42 0.328157

Mughabghab et al. \[Mu81\] 0.420.04

Roy L et al. \[Ro57\] 0.490.10

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