Nd-144

Reviewed by T. Nakagawa, JAERI, March 2003

# 1. Files

***ENDF/B-VI***: Evaluation was made by Schenter et al. in 1980. Their
results were adopted in ENDF/B-VI.

***JENDL-3.3***: In 1984, the evaluation was made by JNDC FPND working
group for JENDL-2. The data were revised in 1990 \[Ka92\] for JENDL-3.1.
The resonance parameters were updated \[Ka01\] for JENDL-3.2. JENDL-3.3
is the same as JENDL-3.2.

***JEFF-3.0***: JEF-2.2 adopted RCN-3 evaluation. The resonance
parameters were updated in 1986. The charged particle emission cross
sections were included in 1989 adopting REAC-ECN-4. Resonance parameters
were updated in 1990. JEFF-3.0 is the same as JEF-2.2.

***CENDL-3***: New evaluation was made in 2000 by Shen et al. \[Sh01\]

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

# 2. Thermal and resonance region

The resonance parameters are summarized in Table 1.

***ENDF/B-VI***

Resolved resonance parameters compiled by Mughabghab et al. \[Mu73\]
were adopted. Background cross sections were given to the capture and
elastic scattering cross sections.

Unresolved resonance parameters were not given.

***JENDL-3.3***

Resolved resonance parameters were evaluated on the basis of Tellier et
al. \[Te71\] and Musgrove et al. \[Mu77\]. Average radiative widths of
47 and 41 meV were assumed for the s- and p-wave resonances,
respectively. The parameters of a negative resonance were adjusted so as
to reproduce the thermal cross sections of 3.60.3 barns recommended by
Mughabghab et al. \[Mu81\]

Unresolved resonance parameters were given to reproduce the cross
sections calculated with the optical model code CASTHY in the energy
range from 12 to 100 keV. Strength functions were calculated with
CASTHY, and level spacing was adjusted to the capture cross section.

***JEFF-3.0***

Based on the recommendation by Mughabghab et al. \[Mu81\]

Unresolved resonance parameters were given in the energy range from 12
to 50 keV together with background cross sections.

***CENDL-3***

JENDL-3.2 was adopted.

Thermal cross sections and resonance integral of capture cross section
are listed in Table 2. ENDF/B-VI gives the resolved resonance parameters
for the single-level Breit-Wigner formula. Therefore, the elastic
scattering and total cross section have negative values at some
energies.

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

***JENDL-3.3*** is recommended.

# 3. Fast neutron region

**(1) Methodology**

***ENDF/B-VI***

Theoretical calculation was performed using Moldauer potential \[Mo63\].
Inelastic scattering cross sections were calculated with the COMNUC-3
code considering 8 discrete levels. The capture cross section was
calculated with the NCAP code. Adjustment of the capture cross section
was made by considering integral and differential data. No threshold
reactions were considered.

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

Evaporation spectra were given to the inelastically scattered neutrons.

***JENDL-3.3***

The total, elastic and inelastic scattering, and capture cross sections
were calculated with the spherical optical model and statistical model
code CASTHY. The gamma-ray strength function was determined so as to
reproduce the capture cross section of 70 mb at 30 keV \[Mu78, Ko78\].
For the inelastic scattering, 5 levels were considered. Direct inelastic
scattering was calculated with the DWUCK-4 code. The direct/semi-direct
capture was calculated from a simple formula of Benzi and Reffo \[Be69\]

Other reaction cross sections were calculated with the preequilibrium
and multi-step evaporation model code PEGASUS. The (n,p) and (n,)
reaction cross sections were normalized to 12 mb recommended by Forrest
\[Fo86\] and 5.4 mb \[Gu83, Qa84\] at 14.5 MeV, respectively.

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

***JEFF-3.0***

All cross section data were calculated with the SASSI-ECN code using
optical potential of Igarasi et al. \[Ig74\] Charged particle emission
cross sections were included from REAC-ECN-4 library.

***CENDL-3***

Calculated with the SUNF code. Optical model parameters were determined
with the APMN code considering various experimental data. Contributions
from direct process were calculated with the DWUCK4 code.

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Nd144.htm#mt1)Nd144.htm#mt1
and Fig. A1

JENDL-3.3 is not in good agreement with experimental data of Shamu et
al. \[Sh80\] above 1 MeV. ***The Other evaluations*** are better than
JENDL-3.3 in the energy range above 1 MeV. However, in the energy range
below 100 keV, ***JENDL-3.3*** is the best.

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Nd144.htm#mt102)Nd144.htm#mt102
and Fig. A2

CENDL-3 has a strange structure around 90 keV, and too large in the
energy range from 100 to 500 keV. ***The Other evaluations*** are almost
the same in the energy range where the experimental data are available..

**(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/Nd144.htm#mt2)Nd144.htm#mt2
and Fig. A3

Two experimental data are available in the MeV region. All evaluations
are almost in agreement with them.

**(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/Nd144.htm#mt4)Nd144.htm#mt4

Discrete levels considered in the evaluations are as follows:

ENDF/B-VI 8 levels up to 2.36 MeV

JENDL-3.3 5 levels up to 1.7913 MeV

JEFF-3.0 14 levels up to 2.218 MeV

CENDL-3 15 levels up to 2.2951 MeV

Direct inelastic was considered for ***CENDL-3*** and ***JENDL-3.3***.
The cross-section shape of ENDF/B-VI is not correct.

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Nd144.htm#mt16)Nd144.htm#mt16

The data of JEFF-3.0 is too large. ***JENDL-3.3*** and ***CENDL-3***
agree well with experimental data.

**(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/Nd144.htm#mt103)Nd144.htm#mt103

***JENDL-3.3*** and ***CENDL-3*** are in good agreement with the
experimental data.

**(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/Nd144.htm#mt107)Nd144.htm#mt107

***CENDL-3*** is in very good agreement with recent experimental data.

**(9) Other reactions**

The following reaction cross sections are given:

ENDF/B-VI None

JENDL-3.3 (n,3n), (n,n), (n,np), (n,nd), (n,nt), (n,d), (n,t), (n,^3^He)

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

CENDL-3 (n,3n), (n,n), (n,np), (n,d), (n,t), (n,^3^He)

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

***CENDL-3*** is recommended except for the capture cross section.
***JENDL-3.3*** is recommended for the capture cross section. However,
the total cross section of CENDL-3 is too small in the energy range from
100 keV to 1 MeV.

# References

\[Be69\] Benzi V. and Reffo G.: *CCDN-NW/*10 (1969).

\[Ca68\] Cabell M.J. et al.: *J. Inorg. Nucl. Chem.*, **30**, 897
(1968), EXFOR21467.

\[Fo86\] Forrest R.A.: *AERE-R* 12419 (1986).

\[Gu83\] Gumca S. et al.: *Acta Phys. Solvoca*, **33**, 9 (1983).

\[Ig74\] Igarasi S. et al.: *JAERI-M* 5752 (1974).

\[Ka92\] Kawai M. et al.: *J. Nucl. Sci. Technol.*, **29**, 195 (1992).

\[Ka01\] Kawai M. et al.: *J. Nucl. Sci. Technol.*, **38**, 261 (2001).

\[Ko78\] Kononov V.N. et al.: *Sov. J. Nucl. Phys.*, **27**, 5 (1978).

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

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

\[Mu77\] Musgrove A.R.de L. et al.: *AAEC/E*401 (1977).

\[Mu78\] Musgrove A.R.DeL. et al.: 78Harwell, p.449 (1978).

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

\[Mu01\] Mughabghab S.F.: *INDC(NDS)*-424, p.69 (2001).

\[Po52\] Pomerance H.: *Phys. Rev.*, **88**, 412 (1952), EXFOR11507.

\[Qa84\] Qaim S.M.: *Radiochim. Acta*, **35**, 9 (1984).

\[Sh80\] Shamu R.E. et al.: *Phys. Rev.* **C22**, 1857 (1980),
EXFOR10615.

\[Sh01\] Shen Q. et al.: *Commun. Nucl. Data Prog.*, **25**, 29 (2001).

\[Te71\] Tellier H.: *CEA-N-*1459 (1971).

\[Ve74\] Vertebnyj V.P. et al.: *YFI*-17, 37 (1974), EXFOR40290.

Table 1 Summary for Resolved and Unresolved Resonance Region: Nd-144

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

Library RRP URP Remarks

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

ENDF/B-VI 9.9996 keV, SLBW No URP

JENDL-3.3 12 keV, MLBW 100 keV

JEFF-3.0 12 keV, MLBW 50 keV

CENDL-3 12 keV, MLBW 100 keV JENDL-3.2 was adopted

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

Table 2 Thermal Cross Sections and Resonance Integral: Nd-144

Unit: barns

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

Library/Experiment Total Elastic Capture Res.Integ.

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

ENDF/B-VI 0.964 4.564 3.600 5.49

JENDL-3.3, CENDL-3 4.604 1.001 3.603 4.30

JEFF-3.0 3.842 0.259 3.582 4.20

Mughabghab et al. \[Mu81,Mu01\] 1.00.2 3.60.3 3.90.5^\*2^

Pomerance \[Po52\] 4.812%^\*1^

Cabell et al. \[Ca68\] 3.580.31^\*1^

Vertebnyj et al. \[Ve74\] 1.00.2

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

\*1 Maxwellian spectrum average

\*2 Calculated from resonance parameters

![](media/image1.wmf){width="8.009722222222223in"
height="6.710416666666666in"}

Fig. A1 Nd-144 total cross section

![](media/image2.wmf){width="8.010416666666666in"
height="6.708333333333333in"}

Fig. A2 Nd-144 capture cross section

![](media/image3.wmf){width="8.010416666666666in"
height="6.708333333333333in"}

Fig. A3 Nd-144 elastic scattering cross section