Nd-142

Reviewed by M. Kawai, KEK, and T. Nakagawa, JAERI, March 2003

# 1. Files

***ENDF/B-VI***: Evaluation was made by Schenter et al. in 1973.

***JENDL-3.3***: In 1984, new evaluation was made by JNDC FPND working
group \[Ao85\] 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 the data of ENDF/B-V. Then, the
resonance parameters were updated in 1988. 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***: 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. Large background cross section was given to the capture
cross section. The elastic scattering cross section has also the
background cross section, but it is very small.

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. \[Mu77\] for JENDL-2. Average radiative
widths of 78 meV and 46 meV were assumed for the s- and p-wave
resonances, respectively. These resonance parameters were modified so as
to reproduce the capture area data measured by Musgrove et al., by
taking account of the correction factor of 0.967 announced by Allen et
al. \[Al82\]. The parameters of a negative resonance and scattering
radius were adjusted so as to reproduce the thermal cross sections
recommended by Mughabghab et al. \[Mu81\]

Unresolved resonance parameters were given in the energy range from 26
to 100 keV. Neutron strength functions S~0~ and S~1~ were based on the
compilation of Mughabghab et al. \[Mu81\] and S~2~ was calculated with
CASTHY. Radiation widths were also based on the compilation of
Mughabghab et al. Level spacing was determined so as to reproduce the
capture cross sections calculated with CASTHY.

***JEFF-3.0***

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

No unresolved resonance parameters were given.

***CENDL-3***

JENDL-3.2 was adopted.

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

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

***JENDL-3.3*** is recommended. URP should be modified so as to
reproduce the capture cross section of ENDF/B-VI. See the recommendation
for the fast energy region.

# 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. No threshold reactions were considered.

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

Evaporation spectra were given to the inelastic scattering to continuum
levels (MT=91).

***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 59 mb at 30 keV \[Mu78, Al82\].
For the inelastic scattering, 11 levels were considered. Direct
inelastic scattering to the first 2+ and 3- levels was calculated with
the DWUCK-4 code, using deformation parameters compiled by Raman et
al.\[Ra87\] and Spear\[Sp89\]. 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 13.8 mb and 6.8 mb
recommended by Forrest \[Fo86\] 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***

ENDF/B-V was adopted. Then charged particle emission cross sections were
taken from REAC-ECN-4 library.

***CENDL-3***

Calculated with the SUNF code. 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/Nd142.htm#mt1)Nd142.htm#mt1
and Fig. A1

![](media/image1.wmf){width="5.902083333333334in"
height="5.347916666666666in"}As shown in Fig. A1, ***ENDF/B-VI*** and
***JEFF-3.0*** are smaller than Shamu et al. \[Sh80\] in the MeV region,
and in agreement with Wisshak's data \[Wi97\] around 100 keV.
***JENDL-3.3*** and ***CENDL-3*** are in good agreement with the
experimental data. JENDL-3.3 is smaller than Shamu et al. above 8 MeV.

![](media/image2.wmf){width="5.90625in"
height="5.322916666666667in"}Fig. A1 Nd-142 total cross section

Fig. A2 Nd-142 capture cross section

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Nd142.htm#mt102)Nd142.htm#mt102
and Fig. A2

***JENDL-3.3*** and ***CENDL-3*** reproduce the experimental data of
Musgrove et al. \[Mu78\] and Kononov et al. \[Ko77\] which are quite
larger than the most recent data of Wisshak et al. \[Wi97\]
***ENDF/B-VI*** (JEFF-3.0) is in good agreement with Wisshak et al.

**(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/Nd142.htm#mt2)Nd142.htm#mt2
and Fig. A3

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

![](media/image3.wmf){width="5.90625in" height="5.322916666666667in"}

Fig. A3 Nd-142 elastic scattering cross section

**(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/Nd142.htm#mt4)Nd142.htm#mt4

Discrete levels considered in the evaluations are as follows:

ENDF/B-VI 8 levels up to 2.38 MeV

JENDL-3.3 11 levels up to 2.978 MeV

JEFF-3.0 8 levels up to 2.38 MeV

CENDL-3 15 levels up to 2.978 MeV

Direct inelastic was considered for ***CENDL-3*** and ***JENDL-3.3***.
The cross-section shape of ENDF/B-VI and JEFF-3.0 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/Nd142.htm#mt16)Nd142.htm#mt16

***JENDL-3.3*** and ***CENDL-3*** provide this cross section data. Both
are in good agreement with experimental data. ***CENDL-3*** is better
than ***JENDL-3.3***.

**(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/Nd142.htm#mt103)Nd142.htm#mt103

***JENDL-3.3*** and ***CENDL-3*** are in agreement with 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/Nd142.htm#mt107)Nd142.htm#mt107

***JENDL-3.3*** and ***CENDL-3*** are in agreement with 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,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.
***ENDF/B-VI*** is recommended for the capture cross section.

# References

\[Ao85\] Aoki T. Et al. 1985 Santa Fe, Vol. 2, p.1627 (1985).

\[Al82\] Allen B.J. et al: *Nucl. Sci. Eng.*, **82**, 230 (1982)

\[Be69\] 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).

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

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

\[Ko53\] Koehler W. et al.: *Phys. Rev.*, **91**, 597 (1953),
EXFOR12060.

\[Ko77\] Kononov V.N. et al.: *Yadernaya Fizika*, **26**, 947 (1977),
*Sov. J. Nucl. Phys.*, **27**, 5 (1978), EXFOR40520.

\[Mo63\] 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.de L. et al.: 1978Harwell, p.449 (1978).

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

\[Mu03\] Mughabghab S.F.: *INDC(NDS)*-440 (2003).

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

\[Ra87\] Raman S., et al.: *Atom. Data and Nucl. Data Table*, **42**, 55
(1987).

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

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

\[Sp89\] Spear, R.H.: *Atom. Data and Nucl. Data Table*, **36**, 1
(1989).

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

\[Wi97\] Wisshak K. et al. : *KfK* 5967 (1997), EXFOR22388.

Table 1 Summary for Resolved and Unresolved Resonance Region: Nd-142

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

Library RRP URP Remarks

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

ENDF/B-VI 6.8395 keV, SLBW No URP

JENDL-3.3 26 keV, MLBW 100 keV

JEFF-3.0 11.064 keV, MLBW No URP

CENDL-3 26 keV, MLBW 100 keV JENDL-3.2 was adopted

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

Table 2 Thermal Cross Sections and Resonance Integral: Nd-142

Unit: barns

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Library/Experiment Total Elastic Capture Res.Integ.

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

ENDF/B-VI 23.268 4.568 18.700 8.93

JENDL-3.3 26.400 7.700 18.700 8.66

JEFF-3.0 27.150 8.516 18.63 6.16

CENDL-3 26.400 7.700 18.700 8.58

Mughabghab et al. \[Mu81\] 7.70.5 18.70.7 3411

Mughabghab et al. \[Mu03\] 18.70.7 9.01.0

Pomerance \[Po52\] 18.512%^\*1^

Koehler et al. \[Ko53\] 7.50.6

Cabell et al. \[Ca68\] 18.760.73^\*1^

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

\*1 Maxwellian spectrum average