Nd-148

Reviewed by T. Nakagawa, JAERI, March 2004

**1. Files**

***ENDF/B-VI***: Evaluation was made by Schenter et al. in 1980 for
ENDF/B-V.

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

Data were evaluated by JNDC FP Nuclear Data WG for JENDL-2 in 1984
\[Ao85\], and modified 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***:

JEFF-3.0 is the same as JEF-2.2. RCN evaluation was adopted to JEF-2.2.
Charged particle emission cross sections were adopted from REAC-ECN-4.

***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 in BNL-325 3rd edition \[Mu73\] were
adopted. Background cross section (1/v type) was added to the capture
cross section. Very small background cross section was given to the
elastic scattering. Since the SLBW formula was adopted, negative values
are found in the elastic scattering cross section.

No unresolved resonance parameters were given.

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

Neutron widths were taken from Tellier \[Te71\], and radiation widths
were based on the capture area data measured by Musgrove et al.
\[Mu77\]. A negative resonance was added so as to reproduce the thermal
capture cross section of 2.5 barns.

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

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

RCN evaluation was based on the data of Musgrove et al. \[Mu77\] and
Mughabghab et al. \[Mu73\]. Spin values of p-wave resonances were
reassigned for JEF. Background was given to the capture cross section.

Unresolved resonance parameters were given up to 50 keV. The cross
sections in this region were calculated with FISPRO-ECN and SASSI-ECN
codes..

***CENDL-3***

Resonance parameters were taken from JENDL-3.2, and those of the
negative and low-laying levels were modified so as to reproduce the
thermal cross sections \[Mu81, Mu03\].

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

***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 capture, THRESH for threshold
reactions and NCAP for capture. Angular distributions of neutrons were
assumed to be isotropic except for the elastic scattering.

***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 gamma-ray strength function was adjusted to the capture
cross section of 100 mb at 50 keV \[Cr82\]. Direct inelastic process was
calculated with DWUCK-4 code to the first 2+ and 3- levels. 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,α) reaction
cross sections were normalized to the systematics and recommendation of
Forrest \[Fo86\] at 14.5 MeV, respectively. 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***

All cross section data of RCN evaluation were calculated with SASSI-ECN
code. Charged- particle production data were taken from REAC-ECN-4
library.

***CENDL-3***

Theoretical calculation was performed with SUNF and DWUCK4 codes.
Calculated data were adopted after comparison with available
experimental data. For the capture cross section, the data fitted to the
experimental ones were adopted below 3 MeV.

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Nd148.htm#mt1)Nd148.htm#mt1,
Fig. A1

Figure A1 shows comparison of evaluated data with experimental data for
Nd-148 and natural Nd. Energy dependence of JENDL-3.3 is not correct in
the MeV region. All the evaluated data are smaller than the data of
Wisshak et al. \[Wi97\] below 200 keV.

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Nd148.htm#mt102)Nd148.htm#mt102,
Fig. A2

***CENDL-3*** seems to be too large around 10 keV. At the high energy
side, ***ENDF/B-VI*** and ***JEFF-3.0*** are too large around 1 MeV.
***JENDL-3.3*** seems to be the best.

**(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/Nd148.htm#mt2)Nd148.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/Nd148.htm#mt4)Nd148.htm#mt4

Discrete levels considered in the evaluations are as follows:

ENDF/B-VI 3 levels up to 0.69526 MeV

JENDL-3.3(=JENDL-3.2) 9 levels up to 1.7240 MeV

JEFF-3.0 (=JEF-2.2) 7 levels up to 1.171 MeV

CENDL-3 11 levels up to 1.5115 MeV

The direct inelastic was calculated for JENDL-3.3 (JENDL-3.2) and
CENDL-3 with DWUCK4 code.

**(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/Nd148.htm#mt16)Nd148.htm#mt16

***CENDL-3*** is in good agreement 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/Nd148.htm#mt103)Nd148.htm#mt103

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

See Fig:
[http://www.nndc.bnl.gov/sg21/fp21/htm/](http://www.nndc.bnl.gov/sg21/fp21/htm/Nd148.htm#mt107)Nd148.htm#mt107

**(9) Other reactions**

The following reaction cross sections are given:

ENDF/B-VI (n,3n), (n,nα), (n,np), (n,d), (n,t), (n,^3^He)

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

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

***JENDL-3*** is recommended. But the total cross section should be
replaced with the data of ***CENDL-3***.

**References**

\[Al67\] Alstad J. et al.: *J. Inorg. Nucl. Chem.*, **29**, 2155 (1967),
EXFOR20044.

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

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

\[Cr82\] Cricchio A. et al.: 1982 Antwerp, p.175 (1982).

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

\[Gr76\] Gryntakis E.M.: private communications (1976) EXFOR 20625. See
also *Radiochim. Acta*, **17**, 191 (1972).

\[He78\] Heft R.E.: 1978 Mayag, p.495 (1978), EXFOR 12866.

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

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

\[Mu73\] Mughabghab S.F. and Garber D.I.: "Neutron Cross Sections Vol.
1, Resonance Parameters," *BNL*-325, 3rd Edition Vol.1 (1973).

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

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

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

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

\[Ru64\] Ruiz C.P. et al.: *Trans. Am. Nucl. Soc.*, **7**, 270 (1964),
EXFOR12049.

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

\[St75\] Steinnes E.: *J. Inorg. Nucl. Chem.*, **37**, 1591 (1975),
EXFOR20635.

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

\[Va74\] Van der Linden R. et al.: *J. Radioanal. Chem.*, **20**, 695
(1974), EXFOR20645.

\[Ve73\] Vertebnyj V.P. et al.: 1973 Kiev, Vol. 2, p.104 (1973),
EXFOR40290.

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

Table 1 Summary for Resolved and Unresolved Resonance Region: Nd-148

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

Library RRP URP Remarks

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

> ENDF/B-VI 912.4 eV, SLBW no urp
>
> JENDL-3.3 8.0 keV, MLBW 8.0 -- 100 keV same as JENDL-3.2
>
> JEFF-3.0 7.7 keV, MLBW 7.7 -- 50 keV same as JEF-2.2
>
> CENDL-3 8.0 keV, MLBW 8.0 -- 100 keV

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

Table 2. Thermal Cross Sections and Resonance Integral: Nd-148

Units: barns

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

Library/Experiment Total Elastic Capture Res.Integ.

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

ENDF/B-VI 2.2019 -0.2985 2.5004 19.5

JENDL-3.3 6.9974 4.5048 2.4925 14.7

JEFF-3.0 3.1628 0.6629 2.4999 19.9

CENDL-3 6.5810 4.0000 2.5809 13.9

Mughabghab et al. \[Mu81\] 4.0±0.5 2.5±0.2^\*1^ 14±1

Mughabghab et al. \[Mu03\] 2.58±0.14 14±1

Pomerance \[Po52\] 3.3±30%^\*2^

Ruiz et al. \[Ru64\] 2.54±0.18^\*2^ 18.7±0.7 (0.5)^\*4^

Alstad et al. \[Al67\] 2.5±0.2^\*2^ 14±2 (0.4)

Vertebnyj et al. \[Ve73\] 4.0±0.5

Van der Linden et al. \[Va74\] 14.0±0.7 (0.55)

Steinnes \[St75\] 14.1±1.3 (0.5)

Gryntakis \[Gr76\] 2.45±0.14^\*2^ 13.77±1.00 (0.55)

Heft \[He78\] 2.58±0.07^\*3^ 16.5±3.0 (0.5)

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

\*1 to ground state.

\*2 Measured in Maxwell spectrum.

\*3 Measured in reactor spectrum.

\*4 Cut-off energy in eV

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

Fig. A1 Nd-148 and Nd-natural total cross section

![](media/image2.wmf){width="8.197222222222223in"
height="7.382638888888889in"}

Fig. A2 Nd-148 capture cross section