WPEC SG 21: Assessment of Neutron Cross-Section Evaluations for the Bulk
of Fission Products

**Dy-163**

Reviewed by Shen Qingbiao CIAE, February, 2004

**1. Files**

***ENDF/B-VI***: Evaluation was made in 1974 for ENDF/B-V. It was
converted to ENDF/B-VI in 1990. The new/modified ENDF/B-VI evaluation
was made in 1998 in which the resolved resonance parameters were
modified.

***JEF-2.2***: ENDF/B-V was adopted. The resonance parameters were
changed from SLBW to MLBW in 1988.. The data were compiled in 1992.

Figs: <http://www.nndc.bnl.gov/sg21/fp21/index.html>

**2. Thermal and resonance region**

\(1\) Resolved resonance parameters

***ENDF/B-VI*** (1.0e-5 eV -- 1.0 keV)

The number of resolved resonances is 115. The resonance parameters were
taken from Mughabghab \[Mu84\].

***JEF-2.2*** (1.0e-5 eV -- 0.48761 keV)

The multi level Breit-Wigner resonance parameters were used. The
resonance parameters were taken from Mughabghab et al.\[Mu73\].

\(2\) Unresolved resonance parameters

***ENDF/B-VI***

No unresolved resonance parameters are given.

***JEF-2.2***

No unresolved resonance parameters are given.

\(3\) Recommendation/conclusion for resonance region

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

**3. Fast neutron region**

\(1\) Methodology

***ENDF/B-VI***

The evaluated data were based on the experimental data and model
calculations.

***JEF-2.2***

The evaluated data were based on the experimental data and model
calculations.

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

The total cross sections of ENDF/B-VI pass through the only experimental
data at around 14 MeV. The shape of the total CS of JEF2.2 at fast
neutron region is not good.

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

The values of ENDF/B-VI are in better agreement with the experimental
data. The values of JEF2.2 are too low.

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

This cross section was obtained as (total cross section) -- (sum of
partial cross sections) in the all

libraries.

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

Excited levels considered in the files.

> ENDF/B-VI 6 levels up to 0.510 MeV
>
> JEF-2.2 6 levels up to 0.510 MeV

No experimental data of total inelastic scattering cross section are
available. Only ENDF/B-VI (JEF2.2) can be chosen. The shape in high
energy region is wrong since no (n,2n) cross sections are given..

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

No (n,2n) cross sections are given for ENDF/B-VI (JEF2.2).

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

No (n,p) cross sections are given for ENDF/B-VI (JEF2.2).

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

No (n, ) cross sections are given for ENDF/B-VI (JEF2.2).

\(9\) Other reactions

The following other reaction cross sections are given in the files.

> JEF-2.2 no
>
> ENDF/B-VI no

\(10\) Recommendation/conclusions for fast neutron region

***ENDF/B-VI*** is recommended. But it has no threshold reaction cross
sections and some reaction cross sections are not good. It needs to be
improved evidently.

**References**

\[Da64\] Danelyan L. S. et al., J, AE, 16(1), 56 (1964).

\[Ho58\] House L. et al., J, BAP, 3, 337(R6) (1958).

\[Lu77\] Lucas M. et al., C, 77Paris, 1, 431 (1977), IAEA-Publ., 475

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

\[Mu73\] Mughabghab S.F. et al, BNL-325, 3ed, V1 (June 1973).:

\[Mu84\] Mughabghab S.F. et al.: "Neutron Cross Sections, Vol.1, Part
B," Academic Press (1984)

\[Sc66\] Scoville J. J., J, NSE, 25, 12 (1966).

\[Ve71\] Vertebnyj V. P. et al., P, YFI-11, 59 (1971).

\[Wa56\] Walker W. H., T, Walker 1956

Table 1. Summary for Resolved and Unresolved Resonance Region: Dy-163

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

Library RRP URP Remarks

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

ENDF/B-VI 1.0 keV MLBW No URP

JEF-2.2 0.48761 keV MLBW No URP

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

Table 2. Thermal Cross Sections and Resonance Integral: Dy-163

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

Library/Experiment Total Elastic Capture Res.Integ.

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

ENDF/B-VI 127.66 3.39 124.27 1489

JEF-2.2 134.370 0.0 134.370 1435

Mughabghab et al. \[Mu84\] 127.2 3.20.5 1247 1470100

Mughabghab \[Mu03\] 1347 1470100

Scoville et al. \[Sc66\] 12119\*1

Lucas et al. \[Lu77\] 305

Vertebnyj et al. \[Ve71\] 12612 9.70.4 11645

House et al. \[Ho58\] 12050\*1

Walker \[Wa56\] 26025\*2

Danelyan et al. \[Da64\] 13513

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

\*1) Maxwellian averaged

\*2) Spectrum averaged