Ce-143

Reviewed by T. Nakagawa, JAERI, January 2003

**1. Files**

***ENDF/B-VI***: Evaluation was made by Schenter et al. in 1974. Their
data were carried over to ENDF/B-VI without any modifications.

***JENDL-3.3***: No data are given.

***JEFF-3.0***: JEF-2.2 adopted the data of ENDF/B-V. The charged
particle emission cross sections were included in 1989 adopting
REAC-ECN-4. JEFF-3.0 is the same as JEF-2.2.

***CENDL-3***: No data are given.

***BROND-2***: No data are given.

**2. Thermal and resonance region**

The resonance parameters are summarized in Table 1.

***ENDF/B-VI***

No resonance parameters are given. The capture cross section at 0.0253
eV was taken from BNL-325 3rd edition \[Mu73\]. In the energy range up
to 101.57 eV, the 1/v type cross section was assumed for the capture and
a constant one for the elastic scattering.

***JEFF-3.0***

ENDF/B-V was adopted (same as ENDF/B-VI).

Thermal cross sections and resonance integral of capture cross section
are listed in Table 2.

**[Recommendation/conclusion for the thermal and resonance
region]{.underline}**

***ENDF/B-VI*** is recommended.

**3. Fast neutron region**

**(1) Methodology**

***ENDF/B-VI***

Theoretical calculation was performed using the optical potential
parameters of Moldauer \[Mo63\]. Inelastic scattering cross sections
were calculated with the COMNUC-3 code. No discrete levels were
considered. The capture cross section was calculated with the NCAP code.
No threshold reaction cross sections were given.

The angular distributions of all reactions were assumed to be isotropic
in the laboratory system.

Evaporation spectra were given to the continuum inelastic scattering.

***JEFF-3.0***

Data were taken from ENDF/B-V. Charged particle emission cross sections
were included from REAC-ECN-4 library.

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Ce143.htm#mt1)Ce143.htm#mt1

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Ce143.htm#mt102)Ce143.htm#mt102

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Ce143.htm#mt2)Ce143.htm#mt2

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Ce143.htm#mt4)Ce143.htm#mt4

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

The cross section of (n,2n) reaction was not given in the both
libraries.

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Ce143.htm#mt103)Ce143.htm#mt103

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Ce143.htm#mt107)Ce143.htm#mt107

**(9) Other reactions**

The following reaction cross sections are given:

ENDF/B-VI no threshold reactions

JEFF-3.0 (n,d), (n,t), (n,^3^He), (n,2p)

**[Recommendation/conclusion for the fast energy region]{.underline}**

***JEFF-3.0*** is recommended.

**References**

\[Mo63\] Moldauer P.A.: *Nucl. Phys.*, **47**, 65 (1963).

\[Mu73\] Mughabghab S.F. and Garber D.I.: *BNL*-325 3rd Edition (1973).

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

\[Ro56\] Roy J.C. et al.: Can. J. Chem., 34, 1238 (1956).

Table 1 Summary for Resolved and Unresolved Resonance Region: Ce-143

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Library RRP URP Remarks

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ENDF/B-VI No RRP No URP 1/v region up to 101.57 eV

JEFF-3.0 No RRP No URP

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Table 2 Thermal Cross Sections and Resonance Integral: Ce-143

Unit: barns

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Library/Experiment Total Elastic Capture Res.Integ.

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ENDF/B-VI 11.0 5.0 6.0 41.5

JEFF-3.0 11.0 5.0 6.0 41.5

Mughabghab et al. \[Mu81\] \-- \-- 6.00.7 \--

Roy et al. \[Ro56\] 6.00.7^\*1^

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\*1 average cross section in a reactor spectrum.