WPEC Subgroup 21

Assessment of Neutron Cross Sections for the Bulk of Fission Products

# Report to the WPEC Meeting, Geel, May 23-24, 2002

P. Oblozinsky^1^, I. Sirakov^1^, R.E. MacFarlane^2^, J. Chang^3^,

T. Nakagawa^4^, K. Shibata^4^, M. Igashira^5^, M. Kawai^6^,

A.V. Ignatyuk^7^, V.G. Pronyaev^8^, V. Zerkin^8^,

Shen Qingbiao^9^ and Zhuang Youxiang^9^

^1^NNDC, Brookhaven, USA, ^2^LANL, Los Alamos, USA, ^3^KAERI, Taejon, S.
Korea,

^4^JAERI, Tokai-mura, Japan, ^5^TIT, Tokyo, Japan, ^6^KEK, Tsukuba,
Japan,

^7^IPPE, Obninsk, Russia, ^8^ IAEA Nuclear Data Section, Vienna,
Austria,

^9^CNDC, Beijing, China

##  Abstract

> Subgroup 21 (SG21) has been approved at the 2001 WPEC Meeting. Since
> then, SG21 Web page was created, informal meeting was held at Tsukuba,
> 101 new fission products evaluations for CENDL-3 were released, trial
> intercomparison package for 20 nuclei was prepared, and trial review
> for 16 of them has been completed. In addition, interactive
> intercomparison plots were prepared for a complete set of 211 nuclei
> in the fission products range (Z = 31 -- 68).

**1. Introduction**

Neutron cross sections of fission products (FPs) constitute a
considerable part of the major evaluated nuclear data libraries. For
example, in the recent release 8 of the US library ENDF/B-VI (October
2001), there are 200 materials that fall into the range of fission
products nuclei (defined as Z = 31 - 68). This should be compared with
the total of 325 materials included in the ENDF/B-VI.

Often, evaluations of many of these materials have not been revised for
a long period of time. As a consequence, analysis of 200 fission
products evaluations in the release 8 of the ENDF/B-VI file reveals the
following situation:

*•* 65% evaluations have been performed more than 20-25 years ago,

*•* 55% evaluations use isotropic neutron elastic angular distribution,

• 30% evaluations use point-wise data in the neutron resonance region,
and

• 30% evaluations use single-level Breit-Wigner representation for
neutron resonances.

A cost-effective solution to this problem has been proposed, namely, to
assess neutron cross sections for fission products by reviewing all
available fission products evaluations, including available experimental
data as included in the EXFOR (CSISRS) library, and considering adopted
evaluation methodology. As a result of this assessment, recommendation
would be made for best evaluations. This methodology is expected to
yield reasonably good results for the bulk of fission products. It is
understood that it is likely to be insufficient for most important
fission products (20-40 depending on the application), where validation
methods should be adopted.

The proposal along these lines was submitted for consideration to the
2001 WPEC Meeting (Santa Fe, April 12-13, 2001). The meeting approved
the proposal and the subgroup 21 has been established. SG21 chair is P.
Oblozinsky, with 4 participants for the ENDF/B library, 4 for JENDL, 3
for BROND and 2 for CENDL (see list of authors of the present report).

Since its approval in April 2001, the SG21 performed the following
activities:

• Prepared SG21 Web page,

• Held informal SG21 meeting on the occasion of the ND2001 conference at
Tsukuba,

• Released 101 new fission products evaluations for CENDL-3 (by CNDC
Beijing),

• Prepared intercomparison package for 20 fission products,

• Reviewed, as a trial step, 16 fission products evaluations, and

• Prepared graphical intercomparison for a complete set of 211 nuclei.

**2. SG21 Web Page**

**Contents.** SG21 Web page for reviewing FP evaluations
([http://www.nndc.bnl.gov/sg21](http://www.nndc.bnl.gov/sg21/)) has been
created and is being maintained by BNL. This Web site contains
background information on the project, shows documents about SG21
activity, it offers links to available, ongoing or planned FP
evaluations, and it presents intercomparisons as well as
reviews/assessments of the evaluations.

**SG21 Meeting at Tsukuba**. Informal Meeting was held at Tsukuba on
October 10, 2001. Discussed was a sample case of ^131^Xe. It was decided
to proceed with a trial review of 20 nuclei. To this end, BNL promised
to prepare intercomparison package.

**CENDL-3 Fission Products File.** CENDL-3 FP file, issued on October 7,
2001 comprises 101 new evaluations for 100 isotopes (Z=31÷66, A=69÷164)
in addition to the two evaluations (^107,\ 109^Ag) carried over from
CENDL-2. The new evaluations are ^69,\ 71^Ga; ^83,\ 84,\ 85,\ 86^Kr;
^85,\ 87^Rb; ^88,\ 89,\ 90^Sr; ^89,\ 91^Y; ^93,\ 95^Zr; ^93,\ 95^Nb;
^95,\ 97,\ 98,\ 100^Mo; ^99^Tc;
^99,\ 100,\ 101,\ 102,\ 103,\ 104,\ 105^Ru; ^103,\ 105^Rh;
^105,\ 108^Pd; ^113^Cd; ^115^In; ^121,\ 123,\ 125^Sb; ^130^Te;
^127,\ 129,\ 135^I; ^123,\ 124,\ 129,\ 131,\ 132,\ 134,\ 135,\ 136^Xe;
^133,\ 134,\ 135,\ 137^Cs; ^130,\ 132,\ 134,\ 135,\ 136,\ 137,\ 138^Ba;
^139^La; ^136,\ 138,\ 140,\ 141,\ 142,\ 144^Ce; ^141^Pr;
^142,\ 143,\ 144,\ 145,\ 146,\ 147,\ 148,\ 150^Nd;
^147,\ 148,\ 148m,\ 149^Pm;
^144,\ 147,\ 148,\ 149,\ 150,\ 151,\ 152,\ 154^Sm;
^151,\ 153,\ 154,\ 155^Eu; ^152,\ 154,\ 155,\ 156,\ 157,\ 158,\ 160^Gd;
and ^164^Dy.

**3. Intercomparisons**

Sample intercomparison of evaluated and experimental data was created
for ^131^Xe. This was followed by a broader trial intercomparison
package created for 20 FPs. Afterwards, graphical intercomparison was
prepared for a complete set of 211 FPs.

**3.1 BNL Intercomparison Package for 20 Fission Products**

Intercomparison Package for 20 Fission Products was prepared by BNL
according to the SG21 requirements. It includes evaluations and EXFOR
data for the following nuclides chosen randomly from the whole FP mass
region: ^69^Ga, ^77^Se, ^83^Kr, ^88^Sr, ^95^Zr, ^97^Mo, ^102^Ru,
^108^Pd, ^113^Cd, ^125^Sb, ^135^I, ^131,132^Xe, ^130,132^Ba, ^144^Ce,
^148^Pm, ^152^Sm, ^152^Gd, and ^164^Dy. Evaluations from the newly
issued CENDL-3 FP file are available for all these nuclides except of
^77^Se. The package was equipped with options for static and interactive
plots in January 2002.

For each nuclide, the intercomparison package provides:

-   Plots for total, capture, elastic, inelastic, (n,2n), (n,p), and
    (n,α) cross sections (MF=3 MT=1, 102, 2, 4, 16, 103, 107), comparing
    5 evaluated libraries (ENDF/B-VI, JENDL-3.2, JEF-2.2, BROND-2.2,
    CENDL-3) and EXFOR/CSISRS data,

-   Summary for the resolved and unresolved resonance region,

-   Experimental and evaluated thermal cross sections, and

-   Remarks.

The graphs which represent MF=3 files of all available evaluations along
with the retrieved experimental data, have been prepared by making use
of the EXFOR (CSISRS) retrieval software
(<http://www.nndc.bnl.gov/nndc/exfor/>) as well as of the ZVView graphic
software
([[http://www-nds.or.at/ndspub/zvview/]{.underline}](http://www-nds.iaea.or.at/ndspub/zvview/)).
The Summary for the resolved and unresolved resonance region provides
information about the year of evaluation, authors, boundaries of the
regions in the evaluated files, and formalisms used. Reasons for the
differences between the evaluated files are suggested for some nuclides
in Remarks.

The intercomparison deals with the thermal point, resolved resonance
region, unresolved resonance region and the fast energy region. These
specifications were formulated by the SG21 meeting in Tsukuba after
discussion of the sample case for ^131^Xe. A 70-group representation,
used in validation of the JENDL-3 library, has also been under
consideration for the resonance region.

The intercomparison menu, available for each nuclide, includes page for
general view of all cross section plots, pages for full-screen plots and
pages for summary and remarks. Interactive and non-interactive modes are
available. Interactive mode allows rearrangement of the scale, energy
region, legends, colors and appearance of evaluated and experimental
data by the reviewer. To this end, one has to install the ZVView Graphic
Software for Nuclear Data Analysis, for reference see above.

**3.2 Graphical Intercomparison for 211 Fission Products**

Graphical intercomparison for a complete set of 211 fission products was
prepared using techniques developed by V. Zerkin, IAEA Vienna. A link to
all plots is available on the SG21 Web page. The intercomparison
includes data from 5 evaluated libraries and EXFOR for 7 most important
reaction channels, (n, tot), (n, el), (n, inl), (n, 2n), (n, γ), (n, p),
and (n, α) (MF=3, MT=1, 2, 4, 16, 102, 103, 107). Furthermore, expanded
plots are provided for total and capture cross sections. This makes
altogether 9 plots per nucleus, totaling to almost 1,900 plots in the
whole package.

Convenient access to evaluated files as well as to EXFOR files is
readily available. This allows reviewer an easy cross communication with
evaluated and experimental information.

An example of intercomparison plots is shown below in connection with
the review report for ^102^Ru.

**4. Review and Assessment**

A key part of the SG21 activity is to review fission products cross
section evaluations, and to make assessment as to which of them are the
best. Review methodology is being developed along several steps. At the
moment, SG21 is at its second step.

**First step**. The review process started with a sample case of ^131^Xe
prepared by BNL, considering two basic review principles:

-   Intercomparison of evaluated and experimental cross sections, and

-   Analysis of evaluation methodology.

This sample case was discussed at Tsukuba, and based on that the second
step was undertaken.

**Second step**. A trial review was undertaken for 20 FPs by the whole
SG21. To this end, BNL prepared (i) Intercomparison package described
above, and (ii) Guidance for reviewer along with two sample reviews
(^77^Se and ^88^Sr). The guidance for reviewer recommends that a
reviewer proceed along the following main points:

1.  Perform initial analysis, inspect intercomparison plots. Check all
    evaluations, check EXFOR data for completeness and correctness.

2.  Check other experimental data since often little or no isotopic data
    for fission products are available in EXFOR.

3.  Analyze thermal cross sections (total, capture, elastic).

4.  Analyze resolved resonance & unresolved resonance region (total,
    capture, elastic).

5.  Analyze fast neutron region, focus on total, capture, elastic
    inelastic, (n,2n), (n,p) and (n,α) cross sections.

6.  Analyze evaluation methodology, consider year of origin and
    reputation of evaluator, consider physics, codes and parameters,
    consider completeness of evaluation.

7.  Write short report, list findings, state recommendation for the best
    evaluation or any other conclusion as appropriate.

So far, 16 reviews were performed. Involved were reviewers from the
whole SG21 team. All reviews, along with their recommendations and
conclusions, are available on the SG21 Web page (see Review and
Assessment).

As an example of fairly detailed review we reproduce in **Attachment 1**
the review report for ^102^Ru prepared by T. Nakagawa (JAERI). This is
complemented with intercomparison plots for ^102^Ru in **Attachment 2**.

For convenience, recommendations for 16 reviewed FPs performed so far
are summarized in **Attachment 3**. It is seen that in most cases
reviewers recommend to adopt recent evaluations from JENDL-3 and
CENDL-3.

**Third step**. This is assumed to be a future step. The trial review,
including methodology, reviews and recommendations will be subject to
discussion by the SG21 participants. As a result, the methodology should
be finalized and SG21 should proceed with full-scale review.

**5. Conclusion**

SG21 has been established a year ago, in April 2001. Since then, it has
made a good progress. In particular, it created SG21 Web page, prepared
extensive intercomparison, and started with actual review and assessment
work. This will be focus of SG21 activity in 2003.

**[Attachment 1]{.underline}**

**Ru-102**

Reviewed by T. Nakagawa, JAERI, February, 2002

**1. Files**

***ENDF/B-VI***: Evaluation was made in 1980 for ENDF/B-V. The results
were the same as ENDF/B-IV. The resonance parameters were revised in
1992 for ENDF/B-VI.

***JENDL-3.2***: In 1984, the evaluation was made for JENDL-2. JENDL-2
data were revised in 1990 for JENDL-3.1. JENDL-3.2 is the same as
JENDL-3.1.

***JEF-2.2***: ENDF/B-V was adopted. In 1989, the charged particle
emission cross sections were adopted from REAC-ECN-4.

***CENDL-3***: Evaluation was performed in 1999. The data were compiled
in 2001.

***BROND-2***: The evaluation was made in1984.

**2. Thermal and resonance region**

\(1\) Resolved resonance parameters

***ENDF/B-VI*** (1.0e-5 eV -- 13.4 keV)

The resolved resonance region is up to 13.4 keV. The parameters were
determined on the basis

of recommendation of Mughabghab et al. \[Mu81\], experimental data of
Macklin and Halperin

\[Ma80\], and Anufriev et al. \[An85\]. The levels between 1.7 and 2.66
keV were fictitious.

***JENDL-3.2*** (1.0e-5 eV -- 13.4 keV)

The evaluation for JENDL-2 was based on the data of Priesmeyer and Jung
\[Pr72\], Shaw et al.

\[Sh75\], and Macklin and Halperin \[Ma80\]. Some levels below 2.6 keV
are fictitious.

They were revised by considering the data of Anufriev et al. \[An85\]
for JENDL-3. Neutron

widths of other levels were also modified.

***JEF-2.2*** (1.0e-5 eV -- 1.61 keV)

Taken from ENDF/B-V. Only 3 resonance levels are given.

***CENDL-3*** (1.0e-5 eV -- 13.4 keV)

ENDF/B-VI was adopted.

***BROND-2*** (1.0e-5 eV -- 1.3 keV)

The recommendation of Mughabghab et al. \[Mu81\] was adopted.

\(2\) Unresolved resonance parameters

***ENDF/B-VI*** (13.4 -- 100 keV)

Determined so as to reproduce the average capture cross section measured
by Macklin and

Halperin \[Ma80\].

***JENDL-3.2*** (13.4 -- 100 keV)

Determined so as to reproduce the capture and total cross section
calculated with CASTHY

code. This calculation is in good agreement with the capture cross
section of Macklin and

Halperin \[Ma80\]

***JEF-2.2***

No unresolved resonance parameters are given.

***CENDL-3*** (13.4 -- 100 keV)

ENDF/B-VI was adopted.

***BROND-2*** (1.3 -- 100 keV)

No information.

\(3\) Recommendation/conclusion for resonance region

The data of JEF-2.2 and BROND-2 are too old. The total and capture cross
sections calculated

from these two files are different from other evaluations (see Figs. 1
and 2). ***JENDL-3.2*** and

***ENDF/B-VI*** (***CENDL-3***) are in the same quality.

**3. Fast neutron region**

\(1\) Methodology

***ENDF/B-VI***

Theoretical calculation was widely used. The optical potential of
Moldauer was adopted.

Inelastic scattering was calculated with COMNUC-3 code, and the capture
cross section with

NCAP code. No direct inelastic was considered. No threshold reaction
cross sections are given.

Legendre coefficients of elastically scattered neutrons were calculated
from Moldauer potential.

Isotropic distributions were given to the inelastic scattering.

Evaporation spectra were given to the continuum inelastic scattering.

***JENDL-3.2***

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 measured by
Macklin et al. \[Ma81,

Ma79\]. The 17 levels up to 2.4419 MeV were considered for the inelastic
scattering. Direct

inelastic scattering cross sections were calculated with DWUCK-4 to the
first 2+ and 3-- levels.

Other reaction cross sections were calculated with a preequilibrium and
multi-step evaporation

code PEGASUS. The (n,p) and (n,α) 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.

Angular distributions of elastic and inelastic scattering were
calculated with CASTHY code,

and those of direct inelastic with DWUCK-4 code. Isotropic distributions
were assumed to the

other reactions.

The energy distributions were calculated with PEGUSUS code.

***JEF-2.2***

ENDF/B-V and REAC-ECN-4 data were adopted.

***CENDL-3***

Calculated with SUNF code and DWUCK-4 code. The optical model parameters
were

determined with APMU code. The 6 levels up to 1.581 MeV were considered
for the inelastic

scattering.

Angular and energy distributions of neutrons were also calculated with
SUNF code.

***BROND-2***

JENDL-1 was adopted in the energy region above 100 keV, except for the
capture cross section

which was modified with the data of Belanova et al. \[Be84\] and direct
capture cross section.

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

Fig: http://www.nndc.bnl.gov/sg21/fp/nucl/ru102/ru102tot.htm

No experimental data are available for Ru-102 total cross section.
Figure 3 compares the

evaluated data with the measured total cross section of natural Ru. From
this figure, it is seen

that ***CENDL-3*** reproduces well the experimental data.

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

Fig.: http://www.nndc.bnl.gov/sg21/fp/nucl/ru102/ru102ng.htm

***BROND-2*** is too large above 100 keV. ***ENDF/B-VI*** is also too
large above 1 MeV. ***JENDL-3.2***

and ***CENDL-3*** are in good agreement with available experimental
data.

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

Fig: http://www.nndc.bnl.gov/sg21/fp/nucl/ru102/ru102el.htm

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)

Fig: http://www.nndc.bnl.gov/sg21/fp/nucl/ru102/ru102inl.htm

Excited levels considered in the files.

> ENDF/B-VI 19 levels up to 2.814 MeV
>
> JENDL-3.2 17 levels up to 2.442 MeV
>
> JEF-2.2 19 levels up to 2.814 MeV
>
> CENDL-3 6 levels up to 1.581 MeV
>
> BROND-2 14 levels up to 2.372 MeV

The shape of total inelastic scattering cross section of ***ENDF/B-VI***
(***JEF-2.2***) and ***BROND-2*** is

not reasonable. That of ***JENDL-3.2*** and ***CENDL-3*** is acceptable.

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

Fig: http://www.nndc.bnl.gov/sg21/fp/nucl/ru102/ru102n2n.htm

***JENDL-3.2*** and ***CENDL-3*** give the (n,2n) reaction cross
section. Their data are discrepant each

other. However, no experimental data are available.

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

Fig: http://www.nndc.bnl.gov/sg21/fp/nucl/ru102/ru102np.htm

***CENDL-3*** reproduces well the data of Gray et al. \[Gr66\] at 14.7
MeV. However, this

experimental data is the cross section of Tc-102m production. Therefore,
real cross section

might be larger than CENDL-3. ***JENDL-3.2*** and ***JEF-2***
(REAC-ECN-4) were normalized to

16.7 mb at 14.5 MeV (Systematics of Forrest \[Fo86\]).

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

Fig: http://www.nndc.bnl.gov/sg21/nucl/ru102/ru102na.htm

***CENDL-3*** adopted the data of JEF-2.2. ***JEF-2.2*** was based on
the data of REAC-ECN-4.

***JENDL-3.2*** was calculated with PEGASUS code and normalized to 6.2
mb at 14.5 MeV

(Recommendation of Forrest \[Fo86\])

\(9\) Other reactions

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

> JENDL-3.2 (n,3n), (n,nα), (n,np), (n,d), (n,t)
>
> CENDL-3 (n,3n), (n,nα), (n,np), (n,d), (n,t), (n,He-3)
>
> JEF-2.2 (n,d), (n,t), (n,He-3), (n,2p)
>
> ENDF/B-VI no
>
> BROND-2 no

JENDL-3.2 dose not give the cross section of (n,He-3) and (n,2p) because
their cross sections

calculated with PEGASUS code were smaller than 0.001 mb.

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

***JENDL-3.2*** or ***CENDL-3*** is recommended. However, the total
cross section of JENDL-3.2 is

not in good agreement with experimental data. The number of levels for
the inelastic scattering

considered in CENDL-3 is too small.

**References**

\[Au85\] Anufriev V.A. et al.: *Sov. At. Energy*, **58**, 328 (1985).

\[Be84\] Belanova T.S. et al.: *At. Energy*, **57**, 243 (1984).

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

\[Gr66\] Gray P.R. et al.: *Nucl. Phys.*, **75**, 215 (1966).

\[He78\] Heft R.E.: 78Mayag, p.495 (1978).

\[Is69\] Ishikawa H.: *J. Nucl. Sci. Technol.*, **6**, 587 (1969).

\[La65\] Lantz P.M.: *ORNL*-3832, p.6 (1965).

\[Ma79\] Macklin R.L. et al.: NEANDC(E) 209"L", p.103 (1979).

\[Ma80\] Macklin R.L. and Halperin J.: *Nucl. Sci. Eng.*, **73**, 174
(1080).

\[Ma81\] Macklin R.L. and Winters R.R.: *Nucl. Sci. Eng.*, **78**, 110
(1981).

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

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

\[Pr72\] Priesmeyer H.G. and Jung H.H.: *Atomkernenergie*, **19**, 111
(1972).

\[Sh75\] Shaw R.A. et al.: *Bull. Am. Phys. Soc*., **20**, 560 (1975).

\[Va72\] Van der Linden R. et al.: *J. Radioanl. Chem.*, **11**, 133
(1972).

Table 1. Summary for Resolved and Unresolved Resonance Region: Ru-102

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

Library RRP URP Remarks

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

ENDF/B-VI 13.4 keV MLBW 100 keV

JENDL-3.2 13.4 keV MLBW 100 keV

JEF-2.2 1.61 keV SLBW No URP taken from ENDF/B-V

CENDL-3 13.4 keV MLBW 100 keV taken from ENDF/B-VI

BROND-2 1.3 keV MLBW 100 keV based on the recommendation of

> Mughabghab et al. \[Mu81\]

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

Table 2. Thermal Cross Sections and Resonance Integral: Ru-102

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

Library/Experiment Total Elastic Capture Res.Integ.

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

ENDF/B-VI 6.794 5.565 1.228 4.33

JENDL-3.2 6.791 5.561 1.229 4.32

JEF-2.2 5.249 3.949 1.300 3.21

CENDL-3.2 6.794 5.565 1.228 4.29

BROND-2 8.075 6.899 1.176 6.30

Mughabghab et al. \[Mu81\] 1.21±0.07 4.2±0.1

Mughabghab \[Mu01\] 1.21±0.07

Lantz \[La65\] 1.23±10%\*2 4.14±10%\*4

Ishikawa \[Is69\] 1.37±0.132\*2

Van der Linden et al. \[Va72\] 4.3±0.4

Heft \[He78\] 1.31±0.03\*1 4.68±0.75

Anufriev et al. \[Au85\]\*3 10.4±0.6 5.5±0.5

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

\*1) Spectrum averaged

\*2) Maxwellian averaged, activation

\*3) Their data have been deleted from EXFOR file.

\*4) Cut-off = 0.54 eV

**[Attachment 2]{.underline}**

[Figure
(http://www.nndc.bnl.gov/sg21/fp/full/...).](http://www.nndc.bnl.gov/sg21/fp21/full/ru102.htm)
Example of Intercomparison Plots for 211 Fission Products: Ru-102.

**[Attachment 3]{.underline}**

Summary of fission products reviews performed by SG21 as of April 24,
2002.

  --------------------------- ------------- ---------------------------- -------------------------------
  **Nuclide\                  **Reviewer\   **Recommendation\            **Recommendation\
   **                          **           for the\                     for the\
                                            Thermal and Resonance        Fast Neutron Region\
                                            Regions\                      **
                                             **                          

  [34-Se- 77](../se77.htm)    I. Sirakov\   ***JENDL-3*** up to 100      ***JENDL-3*** (0.1-20 MeV).\
                              (BNL)         keV.\                        Remark: Discrepancy with
                                                                         Rurarz\'s (n,n') measurement
                                                                         should be explained.\
                                                                          

  [36-Kr- 83](../kr83.htm)    I. Sirakov\   ***CENDL-3*** and            ***CENDL-3*** and ***JENDL-3***
                              (BNL)\        ***JENDL-3*** up to 100      (0.1-20 MeV).\
                                            keV.\                        Remark: CENDL-3 seems not
                                                                         reasonable only for MT=107;
                                                                         JENDL-3 seems not reasonable
                                                                         for MT=2, 4.\
                                                                          

  [38-Sr- 88](../sr88.htm)    I. Sirakov\   ***CENDL-3*** and            ***CENDL-3*** and ***JENDL-3***
                              (BNL)\        ***JENDL-3*** up to 300      (0.3-20 MeV).\
                                            keV.\                        Remark: CENDL-3 somewhat better
                                            Remark: Clarification needed for MT=1, 4.\
                                            regarding validation of       
                                            total cross sections at      
                                            \~100-300 keV.\              
                                                                         

  [40-Zr- 95](../zr95.htm)    I. Sirakov\   ***JENDL-3*** up to 100      ***JENDL-3*** and ***CENDL-3***
                              (BNL)\        keV.\                        (0.1-20 MeV).\
                                                                         Remark: CENDL-3 seems not
                                                                         reasonable for MT=107.\
                                                                          \
                                                                          

  [42-Mo- 97](../mo97.htm)    J. Chang\     ***JENDL-3***                ***CENDL-3*** and ***JENDL-3***
                              (KAERI)\      (***CENDL-3***) up to 100    (0.1-20 MeV).\
                                            keV.\                        Remark: CENDL-3 evaluation
                                            Remark: The RRR and URR need looks more favorable.\
                                            to be reevaluated on the      
                                            basis of Koester1987 and     
                                            Sukhoruchkin1998 data.\      
                                                                         

  [44-Ru-102](../ru102.pdf)   T. Nakagawa\  ***JENDL-3.2*** and          ***JENDL-3.2*** or
                              (JAERI)\      ***ENDF/B-VI***              ***CENDL-3*** (0.1-20 MeV).\
                                            (***CENDL-3***) up to 100    Remark: MT=1 of JENDL-3.2 is
                                            keV.\                        not in good agreement with the
                                                                         experimental data of natural
                                                                         Ru. The number of levels
                                                                         considered for MT=4 in CENDL-3
                                                                         is too small.\
                                                                          

  [46-Pd-108](../pd108.pdf)   K. Shibata\   Difficult to choose the best ***JENDL-3.2*** (0.1-20 MeV).\
                              (KAERI)\      evaluation.\                 Remark: No obvious drawback is
                                            Remark: JEF-2.2 gives too    found in JENDL-3.2 for the
                                            small resonance integral,    reactions considered.\
                                            and should be excluded from   
                                            the selection. For           
                                            ENDF/B-VI.6, the upper limit 
                                            of the RRR should be         
                                            raised.\                     
                                                                         

  [51-Sb-125](../sb125.htm)   M. Kawai\     ***JENDL-3***                ***JENDL-3.2*** or
                              (KEK)\        (***CENDL-3***) up to 100    ***CENDL-3.reevaluation***
                                            keV.\                        (0.1-20 MeV).\
                                            Remark: The estimation of    Remark: MT=1 of JENDL-3.2 is
                                            the thermal capture cross    not in very good agreement with
                                            section seems to be within   experimental data of natural
                                            an accuracy of factor of     Sb. JENDL-3.2 is superior to
                                            two. The value of the new    CENDL-3 and
                                            file Sb125n.C3               CENDL-3.reevaluation in view of
                                            (***reevaluation*** of       physical consistency.\
                                            CENDL-3 reported in private   
                                            communication by Q.Shen in   
                                            2002) is about twice of the  
                                            JENDL-3.2.\                  
                                                                         

  [53-I -135](../i135.htm)    V. Pronyaev\  ***ENDF/B-VI*** up to 10     ***CENDL-3*** (0.2-20 MeV).\
                              (IAEA)\       keV.\                        Remark: CENDL-3 considers
                                            Remark: ***Average resonance different reaction mechanisms
                                            parameters*** for nuclides   and all reaction channels.\
                                            of this region are            
                                            recommended in the range     
                                            10-20 keV.\                  
                                                                         

  [54-Xe-131](../xe131.htm)   Q. Shen\      ***ENDF/B-VI*** up to 80.8   ***CENDL-3.reevaluation***
                              (CNDC)\       keV or                       ([*Xe131n.C3*](../xe131n.c3))
                                            ***CENDL-3.reevaluation***   (0.1-20 MeV).\
                                            ([*new file*](../xe131n.c3)) Remark: CENDL-3 is in better
                                            up to 100 keV.\              agreement with the measured
                                                                         data and takes into account the
                                                                         direct inelastic scattering.\
                                                                          

  [54-Xe-132](../xe132.htm)   Y. Zhuang\    ***JENDL-3***                ***CENDL-3*** or ***JENDL-3***
                              (CNDC)\       (***CENDL-3***) up to 100    (0.1-20 MeV).\
                                            keV.\                        Remark: CENDL-3 probably
                                                                         somewhat better (takes into
                                                                         account the direct inelastic
                                                                         scattering).\
                                                                          

  [56-Ba-132](../ba132.htm)   I. Sirakov\   ***CENDL-3*** up to 100      ***JENDL-3*** (0.1-20 MeV).\
                              (BNL)\        keV.\                        Remark: seems more reasonable
                                                                         than CENDL-3 for MT=4, 102,
                                                                         103, 107.\
                                                                          

  [58-Ce-144](../ce144.pdf)   T. Nakagawa\  ***JENDL-3.2*** up to 100    ***JENDL-3.2*** or CENDL-3
                              (JAERI)\      keV.\                        (0.1-20 MeV).\
                               \                                          
                                                                         

  [64-Gd-152](../gd152.htm)   V. Pronyaev\  ***JENDL-3.2***,             ***JENDL-3.2*** (0.1-20 MeV).\
                              (IAEA)\       ***ENDF/B-VI*** and           
                                            ***CENDL-3*** for the        
                                            thermal value.\              
                                            ***JENDL-3.2***              
                                            (***CENDL-3***) for RRR and  
                                            URR up to 100 keV.\          
                                                                         

  [66-Dy-164](../dy164.htm)   Q. Shen\      ***ENDF/B-VI***              ***CENDL-3*** (0.05-20 MeV).\
                              (CNDC)\       (***CENDL-3***) up to 50     Remark: CENDL-3 is probably in
                                            keV.\                        better agreement with the
                                                                         measured data and takes into
                                                                         account the direct inelastic
                                                                         scattering.\
                                                                          
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