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

**Sr-86**

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***: In 1984, the evaluation was made for JENDL-2. JENDL-2
data were revised in 1990 for JENDL-3.1. 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.

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

**2. Thermal and resonance region**

\(1\) Resolved resonance parameters

***ENDF/B-VI*** (1.0e-5 eV -- 19.942 keV)

The resolved resonance pareameters were taken from BNL-325(1973)
\[Mu73\].

***JENDL-3.2*** (1.0e-5 eV -- 37.12 keV)

The resolved resonance parameters for JENDL-3 were adopted from JENDL-2,
which was evaluated on the basis of the measured data by Camarda et
al.\[Ca70\] and Musgrove et al \[Mu78\].

***JEF-2.2*** (1.0e-5 eV -- 19.942 keV)

Taken from ENDF/B-V, then changed to original single-level.

\(2\) Unresolved resonance parameters

***ENDF/B-VI***

No unresolved resonance parameters are given.

***JENDL-3.2*** (37.12 - 100 keV)

The unresolved resonance parameters for JENDL-3 were adopted from
JENDL-2. The neutron strength function S0, S1, and S2 were calculated
with optical model code CASTHY \[Ig75\] .

***JEF-2.2***

No unresolved resonance parameters are given.

3\) Recommendation/conclusion for resonance region

***JENDL-3.2*** 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.

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

The value and shape of curve of cross sections are acceptable for the 3
libraries.

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

The value and shape of curve of cross sections are acceptable for the 3
libraries. They are agreement with the experimental data and they are
closed each other.

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

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

libraries. They are closed each other.

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

Excited levels considered in the files.

> ENDF/B-VI 7 levels up to 3.19 MeV
>
> JENDL-3.2 13 levels up to 3.1852 MeV
>
> JEF-2.2 7 levels up to 3.19 MeV

The shape and value of curve of total inelastic scattering cross
sections of ***JENDL-3.2*** are reasonable and acceptable. 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.

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

The shape and value of (n,2n) cross sections of ***JENDL-3.2*** are
reasonable and acceptable compared with the experimental data. 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 ***JENDL-3.2*** are
reasonable and acceptable compared with the experimental data. The shape
and value of (n,p) cross sections of ***JEF-2.2*** are not good compared
with the experimental data. No this file for ***ENDF/B-VI***.

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

The value and shape of curve of cross sections are acceptable for
***JENDL-3.2*** and ***JEF-2.2***. No this file for ***ENDF/B-VI***.

\(9\) Other reactions

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

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

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

***JENDL-3.2*** is recommended.

**References**

\[Ca70\] Camarda H., et al., NCSAC-31, 40, 1970.

\[Fo67\] Foglio Para A. et al., J, EN, 14, 228, 1967

\[Gu64\] Gulyas I. et al., C, 64PARIS, 2, 703, 1964.

\[Ha60\] Hans H.S. et al, J, NP, 20, 183, 1060.

\[He78\] Heft R.E., C, 78MAYAG, p.495, 1978.

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

\[Kr65\] Kramer H. H., et al., J, NSE, 22, 373, 1965.

\[Ly60\] Lyon W. S., J NSE, 8, 378, 1960.

\[Ma68\] Mannhart et al., J, ZP, 210, 13, 1968.

\[Mu03\] Mughabghab S.F., Thermal Neutron Capture Cross Sections,
Resonance Integrals and G-Factors, INDC(NDS)-440, February 2003.

\[Mu73\] Mughabghab S.F. et al.: "Neutron Cross Sections, Vol.1,
BNL-325, 3^rd^ ed." (1973).

\[Mu78\] MUSGROVE, A.R. DE L., ET AL.: PROC. INT. CONF. ON NEUTRON
PHYSICS AND NUCL.

DATA FOR REACTORS, HARWELL 1978, 449.

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

\[Se47\] Seren L. et al., J. Phys. Rev., 72, 888 (1947).

Table 1. Summary for Resolved and Unresolved Resonance Region: Sr-86

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

Library RRP URP Remarks

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

ENDF/B-VI 19.942 keV SLBW No URP

JENDL-3.2 37.12 keV MLBW 100 keV

JEF-2.2 19.942 keV MLBW No URP

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

Table 2. Thermal Cross Sections and Resonance Integral: Sr-86

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

Library/Experiment Total Elastic Capture Res.Integ.

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

ENDF/B-VI 2.84 0.0 2.84 5.173

JENDL-3.2 5.173 4.133 1.040 4.82

JEF-2.2 2.84 0.0 2.84 5.173

Mughabghab et al. \[Mu81\] 1.040.07 4.720.24

Mughabghab \[Mu03\] 1.040.07 4.800.3

Foglio Para et al.\[Fo67\] 0.9400.050

Gulyas I. et al. \[Gu64\] 0.7690.048

Hans et al.\[Ha60\] 0.800.25

Heft \[He78\] 0.8160.025

Kramer et al.\[Kr65\] 1.00.1

Lyon \[Ly60\] 1.73

Mannhart et al.\[Ma68\] 0.810.04

Seren L. et al\[Se47\] 1.290.258

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