Nd-147

Reviewed by T. Nakagawa, JAERI, March 2004

**1. Files**

***ENDF/B-VI***: Evaluation was made by Schenter et al. in 1974. The
data below 35 eV were revised by Wright et al. in 1988.

***JENDL-3.3 and JENDL-3.2***:

New evaluation was made by JNDC FP Nuclear Data WG for JENDL-3.1 in 1990
\[Ka92\]. JENDL-3.3 and JENDL-3.2 are the same as JENDL-3.1.

***JEFF-3.0 and JEF-2.2***:

The data of ENDF/B-V was adopted to JEF-2. The resonance parameters were
updated with recommendation of Mughabghab et al. \[Mu81\]. Charged
particle emission cross sections were adopted from REAC-ECN-4. JEFF-3.0
is the same as JEF-2.2.

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

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

**2. Thermal and resonance region**

***ENDF/B-VI***

Resonance parameters recommended by Mughabghab et al. \[Mu81\] were
adopted.

No unresolved resonance parameters were given.

***JENDL-3.3 and JENDL-3.2***

Resolved resonance parameters were based on the recommendation of
Mughabghab et al. \[Mu81\]. A negative resonance was added so as to
reproduce the thermal capture cross section \[Mu81\].

The unresolved resonance parameters were determined from optical model
and statistical model calculation with CASTHY code.

***JEFF-3.0 and JEF-2.2***

Resolved resonance parameters were based on the recommendation of
Mughabghab et al. \[Mu81\]. No unresolved resonance parameters were
given.

***CENDL-3***

Resonance parameters were taken from JENDL-3.2, and modified.

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

Below 35 eV, all the evaluations are in the same quality. Considering
connection to the fast neutron region, ***CENDL-3*** is recommended.

**3. Fast neutron region**

**(1) Methodology**

***ENDF/B-VI***

Theoretical calculations were performed using OMP of Moldauer \[Mo63\],
codes of COMNUC-3 for inelastic and NCAP for capture. No threshold
reactions were condidered. Angular distributions of inelastic neutrons
were assumed to be isotropic.

***JENDL-3.3 and JENDL-3.2***

Theoretical model calculations of total, elastic and inelastic
scattering, and capture were made by using the statistical model code
CASTHY. 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 code PEGASUS. The (n,p) and (n,) reaction
cross sections were normalized to the systematics of Forrest \[Fo86\] at
14.5 MeV. Sum of the threshold reaction cross sections were considered
as a competing reaction cross sections in the CASTHY calculation.

***JEFF-3.0 and JEF-2.2***

The total, inelastic scattering and capture cross sections above 35 eV
are the same as ENDF/B-VI. However, the interpolation of the capture
cross section below 1 keV specified in JEFF (INT=2) is not correct.
Charged-particle production data were taken from REAC-ECN-4 library.

***CENDL-3***

Theoretical calculation was performed with SUNF and DWUCK4 codes.

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Nd147.htm#mt1)Nd147.htm#mt1,
Fig. A1

No experimental data are available for Nd-147. Figure A1 shows the
comparison with the experimental data for natural Nd. If the data of
Nd-147 are almost the same as those of natural Nd, ***JENDL-3.3*** might
be incorrect.

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Nd147.htm#mt102)Nd147.htm#mt102,
Fig. A2

Evaluated data are compared with each other in Fig. A2. Averaged cross
sections are shown in the resolved resonance region. No experimental
data are available.

Maxwellian-averaged cross section was recommended by Toukan et al.
\[To95\]. Table 3 shows comparison of Maxwellian-averaged cross sections
at kT=30 keV. ***CENDL-3*** is the closest to the data of Toukan 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/Nd147.htm#mt2)Nd147.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/Nd147.htm#mt4)Nd147.htm#mt4

Discrete levels considered in the evaluations are as follows:

ENDF/B-VI 3 levels up to 310 keV

JENDL-3.3(=JENDL-3.2) 12 levels up to 792.6 keV

JEFF-3.0 (=JEF-2.2) 3 levels up to 310 keV, same as ENDF/B-VI

CENDL-3 10 levels up to 631.5 keV

The direct inelastic was calculated for ***CENDL-3*** with DWUCK4 code.

Cross section shape of ***ENDF/B-VI*** and ***JEFF-3.0*** is not
reasonable.

**(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/Nd147.htm#mt16)Nd147.htm#mt16

***CENDL-3*** and JENDL-3.3 give this reaction cross section.

**(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/Nd147.htm#mt103)Nd147.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/Nd147.htm#mt107)Nd147.htm#mt107

**(9) Other reactions**

The following reaction cross sections are given:

ENDF/B-VI no other reactions

JENDL-3.3 (JENDL-3.2) (n,3n), (n,n), (n,np), (n,nd), (n,nt), (n,d),
(n,t)

JEFF-3.0 (JEF-2.2) (n,d), (n,t), (n,^3^He), (n,2p)

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

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

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

**References**

\[An79\] Anufriev V.A. et al.: 1979 Koxville, p.907 (1979).

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

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

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

\[He74\] Heck D. et al.: *Atomkernenergie*, **24**, 141 (1974),
EXFOR20556.

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

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

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

\[To95\] Toukan K.A. et al.: *Phys. Rev.*, **C51**, 1540 (1995).

Table 1 Summary for Resolved and Unresolved Resonance Region: Nd-147

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

Library RRP URP Remarks

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

> ENDF/B-VI 35 eV, SLBW no urp
>
> JENDL-3.3 36 eV, MLBW 0.036 -- 100 keV same as JENDL-3.2
>
> JEFF-3.0 35.7 eV, MLBW no urp same as JEF-2.2
>
> CENDL-3 35.2 eV, MLBW 0.0352 -- 100 keV

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

Table 2. Thermal Cross Sections and Resonance Integral: Nd-147

Units: barns

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

Library/Experiment Total Elastic Capture Res.Integ.

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

ENDF/B-VI 524.10 84.21 439.89 574

JENDL-3.3 510.29 79.28 431.02 631

JEFF-3.0 545.58 104.795 439.90 606

CENDL-3 520.31 80.33 439.99 655

Mughabghab et al. \[Mu81\] 440150 405^\*1^

Heck et al. \[He74\] 440150^\*2^

Anufriev et al. \[An79\] 21090^\*3^

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

\*1 Calculated.

\*2 Measured in reactor spectrum.

\*3 Calculated from their resonance parameters.

Table 3. Maxwellian averaged capture cross section of Nd-147

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

Library/Experiment cross section at kT=30 keV(mb)

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

ENDF/B-VI 642

JENDL-3.3 1002

JEFF-3.0 648

CENDL-3 609

Toukan et al. \[To95\] 550150^\*1^

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

\*1 calculated.

![](media/image1.wmf){width="8.197222222222223in"
height="7.382638888888889in"}

Fig. A1 Nd-147 and Nd-natural total cross section

![](media/image2.wmf){width="8.259027777777778in"
height="7.382638888888889in"}

Fig. A2 Nd-147 capture cross section