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

**55-Cs-133 Review**

I. Sirakov, INRNE, March 26, 2003

######## **[Files]{.underline}**

***ENDF/B-VI:*** Year of origin 1971 (ENDF/B-IV), significant revisions:
1978 (fast capture), 1999 (MF=2 re-evaluation)

***JEF-2:*** Year of origin 1982, data taken from RCN evaluation,
significant revisions: 1985, 1986 (MF=2), 1989

***JENDL-3:*** Year of origin 1984, taken from JENDL-2, significant
revision 1990

***CENDL-3:*** Year of origin 1999, revised 2001

######## **[Thermal and resonance region]{.underline}**

***ENDF/B-VI:*** Resolved resonance parameters up to 3.989 keV (Table
1); MLBW representation for the 150 s- and 39 p-wave resonances with
resonance parameters based on BNL-325 (1981) and on measurements by
Nakajima (1990), Macklin(1982) and Popov(1981); scattering radius 5.3 fm
from BNL-325 (1981); 2 negative resonances at -41.3 and -25.2 eV
included to reproduce the thermal capture cross section (Table 2) from
BNL-325 (1981), as well as the measured incoherent (Glaettli 1979) and
coherent (Koester 1978) scattering lengths; L assigned by Bayesian
approach; Unknown spins J assigned randomly assuming level density
proportional to (2J+1); the average radiative width of 123 meV adopted
for 120 s- and all p-wave resonances. Unresolved s-, p- and d-wave
resonance parameters up to 81.607 keV reproduce measured capture cross
sections by Bokhovko(1991), Yamamuro (1983) and Macklin (1982); \<D0\>
and S0 deduced from distribution analysis of the reduced widths, S1 from
systematics, and S2 taken as S0. Computed resonance integral 421 b.

***JEF-2:*** Resolved resonance parameters up to 3.511 keV adopted from
BNL-325 (1981) in 1986; MLBW representation for 167 s- resonances;
Continuous background added for agreement with integral data; 2 bound
levels at -40.76 and -15 eV included; scattering radius 5.3 fm;
SIGMA-ECN code used for calculations in the resolved resonance region.
Unresolved parameters for s-, p- and d-wave presented up to 100 keV;
average radiative width 125 meV; scattering radius 5.5 fm. Computed
resonance integral 438 b.

***JENDL-3*:** MLBW for 325 resolved s-wave resonances up to 5.98 keV;
JENDL-2 resolved resonance parameters, obtained from data measured by
Harvey (1955), Garg (1965), Jung (1970), Thomas (1972), Anufriev (1978)
and Macklin (1982), were modified on the basis of Popov (1981) and
Nakajima's (1990) measurements. Unknown spins J assigned randomly; 2
bound levels at -40.76 and -15 eV adopted from BNL-325 with slightly
adjusted parameters in order to reproduce the thermal capture cross
section from BNL-325 (1981); Average radiative width of 120 meV adopted
for 296 levels; scattering radius of 5.35 fm from BNL-325 (1981).
Unresolved resonance parameters up to 100 keV. S0 taken as recommended
in BNL-325, S1 and S2 strength functions from CASTHY and the effective
scattering radius of 5.84 fm from fitting to the calculated total cross
section at 100 keV. Level spacing determined to reproduce the capture
cross section from CASTHY. Computed resonance integral 396 b.

 

***CENDL-3:*** Resonance parameters taken from JENDL-3.2, except 1) the
neutron width of the background resonance at 5.987 keV, which is 50%
lower than the JENDL-3 value; and 2) the average resonance parameters
(80-100 keV) above the inelastic scattering threshold, which are
significantly changed, mainly by decreasing the average neutron width.
As a result CENDL-3 gives not only a lower evaluation for the inelastic
scattering and a very sharp decrease of the elastic cross section but
also a sharp non-physical decrease of 1.15 b in the total cross section
in order to merge the resonance and fast energy evaluations at the
boundary of 100 keV. Computed resonance integral 396 b.

**Note on the resonance region**: The close values of the one-group
capture cross sections (1E-5 eV - 20 MeV) over fast-reactor weighting
spectrum (<http://www.nndc.bnl.gov/sg21/nucl/acs/accs.htm>) for
***ENDF/B-VI*** (509 mb), ***JEF-2*** (510 mb), ***JENDL-3*** (490 mb)
and ***CENDL-3*** (492 mb) are due to the their close capture cross
sections, mainly in the interval \~50 eV- 100 keV, where the
fast-reactor flux is predominant. Similar trend, but with bigger
discrepancies, appears in their resonance capture integrals.

The sharp total cross-section dip of 1.15 b in the region 80-100 keV,
above the inelastic scattering threshold, is not reasonable in
***CENDL-3*** and makes this evaluation not recommendable. The average
neutron width and, consequently, the total cross section are smooth
functions of the energy and should not change when the competitive
inelastic scattering channel appears (Γn should not depend on Γn').

Compared to ***JENDL-3*** and ***JEF-2***, the total cross-section of
***ENDF/B-VI*** is 0.6-0.7 b lower at the upper boundary of its
resonance region (81.607 keV). This discrepancy can not provide any
recommendation in the absence of experimental data. However, instead of
maintaining the trend from the upper boundary of ***ENDF/B-VI***
resonance region and merging smoothly into the fast energy region
through the available experimental points (\~250 keV) of Barnard (1969),
the ***ENDF/B-VI*** total cross section starts rising sharply and
unreasonably above the inelastic scattering threshold, even by following
the structure of the inelastic scattering cross-section, which is not
acceptable.

Being very close to ***JEF-2*** at the boundary of 100 keV, the elastic
and total cross sections of ***JENDL-3*** have a skip of 50 mb at this
boundary.

**Experimental data** -- All evaluations agree with the EXFOR data on
(n,g) cross sections up to 100 keV, (especially the thermal point data
and those of Widder-1975 below 47 eV and Bokhovko-1991 above 6 keV).
There is also an agreement with the (n,tot) measurements in the interval
0.01-100 eV (Hickman-1965, Landon-1954, Harvey-1955). The resonance
integral data of 437(26) b measured by Steinnes, 1972
([EXFOR20188](http://www.nndc.bnl.gov/htbin/csisrs.cgi?AccNum=20188&DatType=H&RetType=byAccNum&ReDo=N)
013), are in full agreement with ***JEF-2*** value of 438 b as well as
with ***ENDF/B-VI*** value of 421 b. The older resonance integral data
of 370(50) b measured by Brown, 1961
([EXFOR12022](http://www.nndc.bnl.gov/htbin/csisrs.cgi?AccNum=12022&DatType=H&RetType=byAccNum&ReDo=N)
003) are in agreement with ***JENDL-3***(***CENDL-3***) (396 b). As the
elastic scattering is concerned, Koester's 1972 data
([EXFOR20581](http://www.nndc.bnl.gov/htbin/csisrs.cgi?AccNum=20581&DatType=H&RetType=byAccNum&ReDo=N)
007) for a bound coherent scattering length of 5.42(2) fm can be
combined with Glaettli 1979 data for a bound incoherent scattering
length (b~+~-b~-~) of 2.61(30) fm so as to give the zero-energy
scattering cross section of 3.84(6) b. This value is in full agreement
with ***JEF-2*** evaluation of 3.88 b for the zero-energy scattering
cross section, in contrast to ***ENDF/B-VI*** and
***JENDL-3***(***CENDL-3***) values of 3.96 b and 4.30 b respectively.

**Recommendation/Conclusion**: ***JEF-2*** recommended in the resonance
region up to 100 keV. ***JEF-2*** is in full agreement with the capture
resonance integral measured by Steinnes (1972) and, in contrast to all
other evaluations, with the low-energy scattering data of Koester (1972)
and Glaettli (1979). Unlike ***ENDF/B-VI*** and ***CENDL-3***, the total
cross section of ***JEF-2*** shows a reasonable shape above the
inelastic scattering threshold. ***ENDF/B-VI*** has a capture cross
section close to that of ***JEF-2*** and its capture resonance integral
also agrees with Steinnes' (1972) data, which makes ***ENDF/B-VI***
capture cross section (only) also recommendable along with the
***JEF-2*** evaluation.

######## **[Fast neutron region]{.underline}**

-   Methodology

***ENDF/B-VI:*** Spherical OM code ABACUS-NEARREX and Wilmore-Hodgson
parameters for MT=1 with experimental data of Foster (1971);
Hauser-Feshbach calculations with COMNUC. Direct capture by FISPRO code;
MT=16, 103, 107 from THRESH code; MT=16 normalized to the mean value of
Qaim (1970) and Nagel's (1965) data at 14.8 MeV and 14.6 MeV
respectively; 5 discrete levels up to 633 keV considered for the
inelastic scattering. Legendre coefficients from CHAD code to get
anisotropic angular distribution for MF=4, MT=2 in CM system. Account
taken of MT=1, 2, 4, 16, 51-55, 91, 102, 103, 107.

***JEF-2:*** Statistical model code SASSY-ECN and OM calculations with
parameters by Igarasi (1974). High-energy model above 6.5 MeV; Level
density parameter A of 17 MeV^-1^ and 17.3 MeV^-1^ for Cs-133 and Cs-132
respectively. 18 discrete levels up to 942 keV considered for the
inelastic scattering. Legendre coefficients represent the anisotropic
angular distribution for MF=4, MT=2 in CM system. Missing charge
particle production cross sections MT=103, 104, 105, 106, 107, included
in 1989 from REAC-ECN-4 Library. The evaluation adjusted and revised on
the base of reactivity worth integral measurements in the STEK facility
and activation integral measurements in the CFRMF facility. MT=1, 2, 4,
16, 51-68, 91, 102, 103, 104, 105, 106, 107, 111.

***JENDL-3:*** Spherical OM and statistical model code CASTHY for MT=1,
4, 51-91, 102 by taking into account competing reactions MT=16, 17, 103,
107, etc, calculated with the preeq and multi-step evaporation model
code PEGASUS. OM parameters by Igarasi (1974); Level density parameter A
of 17.5 MeV^-1^ and 16.76 MeV^-1^ for Cs-133 and Cs-132 respectively.
The gamma-ray strength function adjusted to measured capture cross
section at 30 keV. Direct and semi-direct capture estimated; 13 discrete
levels up to 917 keV adopted for the inelastic scattering. MT=103 and
MT=107 normalized to recommended by Forrest (1986) 14.5 MeV values of
10.5 mb and 1.6 mb respectively; elastic calculated as (MT1 -- sum of
partial cross sections); Legendre coefficients from CASTHY to get
anisotropic angular distribution for MF=4, MT=2, 51-63 in CM system.
MT=1, 2, 4, 16, 17, 22, 28, 32, 33, 51-63, 91, 102, 103, 104, 105, 106,
107.

***CENDL-3:*** Spherical OM and unified preeq-statistical model code
SUNF; 7 levels up to 705 keV adopted for the inelastic scattering; MT=4,
51-57, 91 calculated with SUNF. Elastic calculated as (MT1 -- sum of
partial cross sections); Experimental data of Foster (1971) and Barnard
(1974) used for the total cross section. Legendre coefficients obtained
to present anisotropic angular distribution for MF=4, MT=2 in CM system.
MT=1, 2, 4, 16, 17, 22, 28, 51-57, 91, 102, 103, 104, 105, 106, 107.

-   MT=1

***JEF-2*** and ***JENDL-3*** are very close except for the region 11-15
MeV where the maximum discrepancy is 150 mb. ***JENDL-3*** is probably
somewhat better for its better agreement with the experimental data of
Foster (1971) between 12 and 14 MeV.

***CENDL-3*** is 0.3 b higher than ***JEF-2/JENDL-3*** evaluations at
\~1 MeV and 1.05 b lower at 100 keV. In the region 0.8 - 1.1 MeV (but
not in the regions 0.4 -- 0.8 MeV and 1.1 - 1.2 MeV) it presents
slightly better fit to Barnard's (1969) data, which are rather scattered
and of large uncertainties. ***CENDL-3*** does not merge into the
recommended resonance evaluation and its low value at the boundary of
100 keV is not reasonable in view of any resonance evaluation (see: Note
on the resonance region).

***ENDF/B-VI*** is not much in agreement with Barnard's data. Merging
the resonance and high energy region of ***ENDF/B-VI*** is also not
reasonable for the sharp increase above the inelastic scattering
threshold.

-   MT=2

***CENDL-3*** and ***JENDL-3*** curves are not smooth above 10 MeV.
***JEF-2*** is very close to ***JENDL-3*** and has the advantage of
being smooth.

The rise of ***CENDL-3*** at the 18.25-MeV peak (16.75 -- 18.25 MeV) is
related to the (n,2n)-decrease of 0.4 b, which is about two times higher
than (n,3n)-growth. The dip for E\>18.25 MeV appears since the
(n,3n)-growth becomes higher than (n,2n)-decrease.

***CENDL-3*** is closer to the elastic cross section at 877 keV measured
by Cox (1972)
([EXFOR10332](http://www.nndc.bnl.gov/htbin/csisrs.cgi?AccNum=10332&DatType=H&RetType=byAccNum&ReDo=N)
110). No information on uncertainties, however, is given for the Cox's
measurement (except resolution of 0.2 MeV), which makes the data less
useful. On the other hand, ***CENDL-3*** is too low at the boundary of
100 keV in view of the resonance evaluation.

***ENDF/B-VI:*** Does not reasonably merge the UR region since the
elastic cross section rises sharply above the inelastic scattering
threshold. Does not merge the recommended resonance evaluation as well.
***ENDF/B-VI*** is higher than ***JEF-2*** and ***JENDL-3*** at energies
12 - 20 MeV at the expense of: lower MT=4, compared to ***JENDL-3***;
lower MT=16 compared to ***JEF-2***; higher MT=1 above 17 MeV; and
neglecting (n,3n)-reaction above 17 MeV.

-   MT=4

***CENDL-3:*** Presents lowest values from the threshold up to 3 MeV,
but highest values above the (n,2n)-threshold of 9 MeV.

***JENDL-3:*** About 0.1 -- 0.4 b lower than ***CENDL-3*** in the region
9 - 20 MeV.

***JEF-2:*** Practically equal to zero above 14.5 MeV.

***ENDF/B-VI:*** Shows a rather peaked shape at 3.5 MeV.

-   MT=16

***JEF-2*** and ***ENDF/B-VI:*** Unrealistic trend of (n,2n) cross
section at high energies; (n,3n) reaction neglected. ***JEF-2*** is also
too far from the experimental points.

***CENDL-3*** and ***JENDL-3:*** Show reasonable shape and a good
agreement with the experimental data, with some preference for
***CENDL-3***. ***JENDL-3*** is about 0.1 -- 0.4 b higher than
***CENDL-3*** in the region 9 - 20 MeV.

-   MT=102

***JEF-2, ENDF/B-VI:*** Agree with the experimental data, including
those (above 10 MeV) of Rigaud (1971), Qaim (1970), and Ma Hui-Fang
(1982) in contrast to ***JENDL-3*** and ***CENDL-3***.

-   MT=103

***JENDL-3, CENDL-3:*** Show reasonable shape and a good agreement with
Qaim's (1970) data of 10.5(16) mb at 14.80(15) MeV.

***JEF-2:*** Too high (15 mb) at 14.8 MeV.

***ENDF/B-VI:*** Does not show a reasonable shape.

-   MT=107

***JENDL-3, CENDL-3:*** Show a reasonable shape and general agreement
with the experimental data.

***ENDF/B-VI, JEF-2:*** Do not show a reasonable shape.

**Recommendation/Conclusion** for the fast energy region 100 keV - 20
MeV: ***JENDL-3*** and ***JEF-2*** recommended for MT=1, with some
preference for ***JENDL-3*** in view of its better agreement with the
experimental data of Foster (1971) between 12 and 14 MeV. ***JEF-2*** is
recommended for MT=2. In the region 0.8 -- 1.1 MeV, MT=1 and MT=2 of
***CENDL-3*** could also be recommended for presenting a better fit to
Barnard (1969) and Cox's (1972) data respectively. ***JENDL-3*** is
recommended also for MT=4, 103, 107, and ***CENDL-3*** for MT=16, 103,
107. Both ***JEF-2*** and ***ENDF/B-VI*** are recommended for MT=102.

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

**[Table 1]{.underline}.** Summary for Resolved and Unresolved Resonance
Region: Cs-133

+---------+---+----------+-------+----+-------------------------------+
| Library | Y | First    | RRR   | U  | Remarks                       |
|         | e | Authors  |       | RR |                               |
|         | a |          |       |    |                               |
|         | r |          |       |    |                               |
+---------+---+----------+-------+----+-------------------------------+
| EN      | 1 | S.Oh     | 3.989 | 81 | MLBW for the 150 s- and 39    |
| DF/B-VI | 9 | (KAERI), | keV\  | .6 | p-wave resonances with        |
|         | 9 | S.Mu     | \     | 07 | parameters based on BNL-325   |
|         | 9 | ghabghab | MLBW  | k  | (1981) and on measurements by |
|         |   | (BNL),   |       | eV | Nakajima (1990),              |
|         |   | R.       |       |    | Macklin(1982) and             |
|         |   | Schenter |       |    | Popov(1981); scattering       |
|         |   | (HEDL)   |       |    | radius 7.1 fm from BNL-325    |
|         |   |          |       |    | (1981); 2 negative resonances |
|         |   |          |       |    | at 41.3 and 25.2 eV included  |
|         |   |          |       |    | to reproduce the thermal      |
|         |   |          |       |    | capture cross section from    |
|         |   |          |       |    | BNL-325 (1981), as well as    |
|         |   |          |       |    | the measured incoherent       |
|         |   |          |       |    | (Glaettli 1979) and coherent  |
|         |   |          |       |    | (Koester 1978) scattering     |
|         |   |          |       |    | lengths; L assigned by        |
|         |   |          |       |    | Bayesian approach; Unknown    |
|         |   |          |       |    | spins J assigned randomly     |
|         |   |          |       |    | assuming (2J+1)-proportional  |
|         |   |          |       |    | level density; the average    |
|         |   |          |       |    | radiative width of 123 meV    |
|         |   |          |       |    | adopted for 120 s- and all    |
|         |   |          |       |    | p-wave resonances;            |
|         |   |          |       |    |                               |
|         |   |          |       |    | URR: Average s-, p- and       |
|         |   |          |       |    | d-wave resonance parameters   |
|         |   |          |       |    | up to 81.607 keV reproduce    |
|         |   |          |       |    | measured capture cross        |
|         |   |          |       |    | sections by Bokhovko(1991),   |
|         |   |          |       |    | Yamamuro (1983) and Macklin   |
|         |   |          |       |    | (1982); \<D0\> and S0 deduced |
|         |   |          |       |    | from distribution analysis of |
|         |   |          |       |    | the reduced widths, S1 from   |
|         |   |          |       |    | systematics and S2 taken as   |
|         |   |          |       |    | S0.                           |
|         |   |          |       |    |                               |
|         |   |          |       |    | Computed resonance integral   |
|         |   |          |       |    | 421 b.                        |
|         |   |          |       |    |                               |
|         |   |          |       |    | .                             |
+---------+---+----------+-------+----+-------------------------------+
| JEF-2   | 1 | Gr       | 3.511 | 1  | Resolved resonance parameters |
|         | 9 | uppelaar | keV\  | 00 | for 167 s- resonances adopted |
|         | 8 | (ECN),\  | \     | k  | from BNL-325 (1981) in 1986;  |
|         | 2 | Menapace | MLBW  | eV | continuous background added   |
|         |   | (ENEA),  |       |    | for agreement with integral   |
|         |   |          |       |    | data; 2 bound levels at       |
|         |   |          |       |    | -40.76 and -15 eV included;   |
|         |   |          |       |    | scattering radius 5.3 fm;     |
|         |   |          |       |    | SIGMA-ECN code used for       |
|         |   |          |       |    | calculations.                 |
|         |   |          |       |    |                               |
|         |   |          |       |    | URR: s-, p- and d-wave        |
|         |   |          |       |    | resonance parameters up to    |
|         |   |          |       |    | 100 keV; average radiative    |
|         |   |          |       |    | width 125 meV; scattering     |
|         |   |          |       |    | radius 5.5 fm. Computed       |
|         |   |          |       |    | resonance integral 438 b.     |
+---------+---+----------+-------+----+-------------------------------+
| JENDL-3 | 1 | JNDC FP  | 5.98  | 1  | RRR: 325 s-wave resonances;   |
|         | 9 | Nuclear  | keV\  | 00 | JENDL-2 resolved resonance    |
|         | 9 | Data     | \     | k  | parameters, obtained from     |
|         | 0 | Working  | MLBW  | eV | data measured by Harvey       |
|         |   | Group    |       |    | (1955), Garg (1965), Jung     |
|         |   |          |       |    | (1970), Thomas (1972),        |
|         |   |          |       |    | Anufriev (1978) and Macklin   |
|         |   |          |       |    | (1982), were modified on the  |
|         |   |          |       |    | basis of Popov (1981) and     |
|         |   |          |       |    | Nakajima's (1990)             |
|         |   |          |       |    | measurements; Unknown spins J |
|         |   |          |       |    | assigned randomly; 2 bound    |
|         |   |          |       |    | levels at -40.76 and -15 eV   |
|         |   |          |       |    | adopted from BNL-325 with     |
|         |   |          |       |    | slightly adjusted parameters  |
|         |   |          |       |    | so that to reproduce the      |
|         |   |          |       |    | thermal capture cross section |
|         |   |          |       |    | from BNL-325 (1981); Average  |
|         |   |          |       |    | radiative width of 120 meV    |
|         |   |          |       |    | adopted for 296 levels;       |
|         |   |          |       |    | scattering radius of 5.35 fm  |
|         |   |          |       |    | from BNL-325 (1981).          |
|         |   |          |       |    |                               |
|         |   |          |       |    | URR: S0 taken as recommended  |
|         |   |          |       |    | in BNL-325, S1 and S2         |
|         |   |          |       |    | strength functions from       |
|         |   |          |       |    | CASTHY and the effective      |
|         |   |          |       |    | scattering radius of 5.84 fm  |
|         |   |          |       |    | from fitting to the           |
|         |   |          |       |    | calculated total cross        |
|         |   |          |       |    | section at 100 keV. Level     |
|         |   |          |       |    | spacing determined to         |
|         |   |          |       |    | reproduce the capture cross   |
|         |   |          |       |    | section from CASTHY.          |
|         |   |          |       |    |                               |
|         |   |          |       |    | Computed resonance integral   |
|         |   |          |       |    | 396 b.                        |
+---------+---+----------+-------+----+-------------------------------+
| CENDL-3 | 1 | Z.Zhang  | 5.98  | 1  | Resonance parameters taken    |
|         | 9 | (NWU),   | keV\  | 00 | from JENDL-3.2, except 1) the |
|         | 9 |          | \     | k  | neutron width of the          |
|         | 9 | X.Sun    | MLBW  | eV | background resonance at 5.987 |
|         |   |          |       |    | keV, which is 50% lower than  |
|         |   | (NWU),   |       |    | the JENDL-3 value; and 2) the |
|         |   |          |       |    | average resonance parameters  |
|         |   | J.W.Zhao |       |    | (80-100 keV) above the        |
|         |   | (NJU),   |       |    | inelastic scattering          |
|         |   |          |       |    | threshold, which are          |
|         |   | W.N.Su   |       |    | significantly changed, mainly |
|         |   |          |       |    | by decreasing the average     |
|         |   | (NJU),   |       |    | neutron width. As a result    |
|         |   |          |       |    | CENDL-3 gives not only a      |
|         |   | Q.Shen   |       |    | lower evaluation for the      |
|         |   | (CNDC)   |       |    | inelastic scattering and a    |
|         |   |          |       |    | very sharp decrease of the    |
|         |   |          |       |    | elastic cross section but     |
|         |   |          |       |    | also a sharp non-physical     |
|         |   |          |       |    | decrease of 1.15 b in the     |
|         |   |          |       |    | total cross section in order  |
|         |   |          |       |    | to merge the resonance and    |
|         |   |          |       |    | fast energy evaluations at    |
|         |   |          |       |    | the boundary of 100 keV.      |
|         |   |          |       |    | Computed resonance integral   |
|         |   |          |       |    | 396 b.                        |
+---------+---+----------+-------+----+-------------------------------+

**[Table 2]{.underline}.** Thermal Cross Sections for Cs-133

+--------------------------------+------------+------------+----------+
| Library / Experiment           | Total      | Capture    | Elastic  |
+--------------------------------+------------+------------+----------+
| ENDF/B-VI                      | 32.973 b   | 29.002 b   | 3.971 b  |
+--------------------------------+------------+------------+----------+
| JEF-2                          | 32.987 b   | 29.094 b   | 3.893 b  |
+--------------------------------+------------+------------+----------+
| JENDL-3                        | 33.323 b   | 29.012 b   | 4.311 b  |
+--------------------------------+------------+------------+----------+
| CENDL-3                        | 33.323 b   | 29.012 b   | 4.311 b  |
+--------------------------------+------------+------------+----------+
| Tattersall (1960)              |            | 28(1) b    |          |
+--------------------------------+------------+------------+----------+
| Carre (1966)                   |            | 28(1) b    |          |
+--------------------------------+------------+------------+----------+
| Goldman (1968)                 |            | 30.0 (15)  |          |
|                                |            | b          |          |
+--------------------------------+------------+------------+----------+
| Hickman (1965)                 | 33.1(8) b  |            |          |
+--------------------------------+------------+------------+----------+
| BNL-325 (1981)                 |            | 29.0(10) b |          |
+--------------------------------+------------+------------+----------+
| S.F.Mughabghab, INDC(NDS)-     |            | 29.0(10) b |          |
|                                |            |            |          |
| 424, p.69 (2001)               |            |            |          |
+--------------------------------+------------+------------+----------+