53-I -129 CAD,BRC,+ EVAL-FEB05 G.NOGUERE, E.DUPONT, E.BAUGE
DIST-JAN09 20090105
----JEFF-311 MATERIAL 5331
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 Updated **
** Modification: Corrections by E. Dupont, CEA **
******************************************************************
Modification of JEFF-3.1
========================-----------------------------------------
2006-07 E.Dupont (CEA)
MF2/MT151 -set AWRI=AWR for LRU=1 (RRR) and LRU=2 (URR)
MF3/MT3 -Deleted
MF3/MT5 -Deleted (cross section for (g,gx) reaction)
MF6/all -Normalization of spectra
MF6/MT5 -Deleted
MF8/all -MATP set to 0
MF9/all -IZAP added
MF9/MT102 -yields for production of ground- and meta-
stable states of 130I
MF10/all -IZAP added
MF10/MT102 -Deleted (move to MF9)
***************************** JEFF-3.1 *************************
New evaluation
MAIN AUTHORS AND CONTRIBUTIONS
==============================-----------------------------------
G. NOGUERE, CEA-DEN/DER/SPRC (Cadarache, France)
+ A. BRUSEGAN, P. SCHILLEBEECKX, JRC-IRMM (Belgium)
A. LEPRETRE, F. Gunsing, CEA/DSM-Saclay (France)
New measurements and evaluation of the resolved and unresolved
resonance ranges up to 27.8 keV.
E. DUPONT, CEA-DEN/DER/SPRC (Cadarache, France)
Continuum modelling, comparison with experimental data,
assembly and verification of the file.
E. BAUGE, CEA-DAM/DPTA/SPN (Bruyeres-le-Chatel, France)
Semi-microscopic deformed optical model potential and
coupled-channels calculations.
+ A. KONING, NRG-Petten (The Netherlands) and
the TALYS development team (NRG-CEA/DAM collaboration)
For constant support and permission to use pre-release versions
of the TALYS and TEFAL codes.
GENERAL INFORMATION
==============================-----------------------------------
* RESONANCE PARAMETERS UPDATED WITH RESULTS EXTRACTED FROM
RECENT EXPERIMENTAL DATA
* NEW DESCRIPTION OF THE UNRESOLVED ENERGY RANGE UP TO 27.8 KEV
* NEW EVALUATION OF THE HIGH ENERGY RANGE UP TO 30 MEV
THERMAL CROSS SECTIONS AND RESONANCE INTEGRALS
==============================-----------------------------------
THERMAL CROSS SECTIONS AND RESONANCE INTEGRALS CALCULATED WITH
THE NJOY-99.90 CODE [McF00]:
| 2200 m/s values | Resonance Integral
| (barns) | (barns)
---------+-----------------+--------------------
Total | 36.9 |
Elastic | 4.4 |
Capture | 32.5 | 33.8
RESOLVED RESONANCE RANGE (RRR): E < 5 KEV
==============================-----------------------------------
* RESOLVED RESONANCE PARAMETERS WERE REPLACED BY REICH-MOORE
PARAMETERS EXTRACTED FROM SIMULTANEOUS ANALYSIS OF
TRANSMISSION AND CAPTURE TIME OF FLIGHT DATA CARRIED OUT AT
THE GELINA FACILITY [Nog04]. RESONANCE SHAPE ANALYSIS WERE
PERFORMED WITH THE REFIT CODE [Mox90] UP TO 10 KEV.
THE VALIDITY OF THE PRESENT RESULTS WERE THEN VERIFIED WITH
THE SAMMY CODE [Lar03]. THE ORBITAL MOMENTUM OF THE 399
RESONANCES HAS BEEN ASSIGNED ON THE BASIS OF THE SUGGESTION
PROVIDED BY THE BAYESIAN APPROACH IMPLEMENTED IN THE ESTIMA
CODE [For83].
* S-WAVE AVERAGE PARAMETERS EXTRACTED FROM THE RRR:
R' = 5.6 +/- 1.6 fm => R0 infinity ~ 0.18
= 106.0 +/- 15.2 meV
S0 = (0.54 +/- 0.07)10^-4
D0 = 27.3 +/- 0.9 eV => a = 16.56 +/- 0.06 1/MeV
a STANDS FOR THE FERMION GAS LEVEL DENSITY PARAMETER
DETERMINED WITH THE GILBERT AND CAMERON FORMULA [Gil65].
* WARNING: RESONANCE PARAMETERS ABOVE 5 KEV ARE GIVEN IN THE
PRESENT FILE FOR INFORMATION ONLY. ABOVE THIS NEUTRON ENERGY,
MANY WEAK LEVELS WERE NOT IDENTIFIED.
UNRESOLVED RESONANCE RANGE (URR): 5 KEV < E < 27.8 KEV
==============================-----------------------------------
* UNRESOLVED RESONANCE RANGE HAVE BEEN ANALYSED WITH THE
GENERALISED HAUSER-FESHBACH FORMALISM IMPLEMENTED IN THE
FITACS OPTION OF THE SAMMY CODE. TRANSMISSION AND CAPTURE
DATA MEASURED AT THE GELINA FACILITY [Nog04] HAVE BEEN
CONVERTED RESPECTIVELY INTO TOTAL AND CAPTURE CROSS SECTIONS
USING THE SHELF-SHIELDING AND MULTIPLE SCATTERING CORRECTIONS
CALCULATED WITH THE MONTE-CARLO CODE SESH [Fro68]. THE UPPER
ENERGY LIMIT OF THE UNRESOLVED RESONANCE RANGE IS SET TO THE
FIRST INELASTIC THRESHOLD (27.8 KEV).
* AVERAGE PARAMETERS EXTRACTED FROM THE URR: THE PRESENT VALUES
HAVE BEEN OBTAINED TO GET A GOOD AGREEMENT BETWEEN URR DATA
AND RESULTS FROM TALYS
s-wave R0 infinity = 0.14
S0 = 0.60
= 108.4 meV
D0 = 27.3 eV
l-wave R1 infinity = -0.2455
S1 = 1.54
= 114.2 meV
D1 = 14.1 eV
THE S-WAVE MEAN LEVEL SPACING COMES FROM THE STATISTICAL
ANALYSIS OF THE RRR.THE P-WAVE MEAN LEVEL SPACING IS THEN
CALCULATED WITH THE GILBERT AND CAMERON FORMULA [Gil65] USING
A SPIN CUT OFF VALUE AS DEFINED IN REF [Her87].
HIGH ENERGY RANGE: 27.8 keV < En < 30 MeV
==============================-----------------------------------
New evaluation based on model calculations using the ECIS-97
and TALYS-0.52 [Kon04] codes with a semi-microscopic deformed
optical model potential [Bau01] for neutrons and folded OMPs --
derived from the default nucleon potentials [Kon03] of TALYS --
for other particles (p, d, triton, helion and alpha).
Nucleus deformation: Beta-2 = 0.13
Channels coupled in a vibrational model within the ECIS code are
indicated in the following 129I levels scheme,
Coupled Spin- Energy
Channels parity (keV)
6 yes 9/2+ _________________________________ 729.57
5 yes 11/2+ _________________________________ 695.89
4 1/2+ _________________________________ 559.62
3 5/2+ _________________________________ 487.35
2 3/2+ _________________________________ 278.38
1 yes 5/2+ _________________________________ 27.80
0 7/2+ _________________________________ 0.00
The level density parameter and the spin cut-off factor used
in the TALYS compound nucleus statistical models were adjusted
to be consistent with the URR average spacing and experimental
capture cross-section.
Average CONT parameters (En~0)
| l=0 | l=1 | l=2
-------------+--------+--------+--------
R' (fm) | 5.69 | 5.69 | 5.69
(eV) | 27.66 | |
Sl *10**4 | 0.62 | 2.11 | 0.47
(meV) | 108.00 | 108.00 | 108.00
The model parameters were fine-tuned to enforce agreement with
experimental data [Exf05]:
- Differential cross-sections: (n,tot), (n,2n), (n,3n), (n,g)
FILE INFORMATION
=================================================================
This file was formated thanks to SAMMY [Lar03] and TALYS [Kon04]
formatting capabilities.
REFERENCES
==============================-----------------------------------
[Bau01] E. Bauge, et al., Phys. Rev. C63, 024607 (2001).
[Exf05] Nuclear Reaction Data Centres Network (NRDC, IAEA),
OECD NEA Data Bank EXFOR retrieval system (2005),
see http://www.nea.fr/html/dbdata/x4/.
[For83] E. Fort and J.P. Doat, NEANDC-161 (1983).
[Fro68] F.H. Frohner, Report Gulf General Atomic GA-8380 (1968).
[Gil65] A. Gilbert and A. Cameron, Can. Jour. Phys. 43(1965)1446.
[Her87] M. Herman and G. Reffo, Phys. Rev. C 36(1987)1546.
[Iga75] S. Igarasi et al., Proc. Conf. on Nuclear Cross Sections
and Technology, Washington DC (1975).
[Kon03] A. Koning, J.-P. Delaroche, Nucl. Phys. A713, 231 (2003).
[Kon04] A. Koning, et al., in Int. Conf. on Nuclear Data for
Science and Technology, Santa Fe, USA, September 2004.
[Lar03] N.M. Larson, Oak Ridge National Laboratory,
ORNL/TM-9179/R6 (2003).
[Mac83] R.L Macklin, Nucl. Sci. Eng. 85(1983)350.
[McF00] R.E. MacFarlane, NJOY99 - Code system for producing
pointwise and multigroup neutron and photon cross
sections from ENDF/B Data, RSIC PSR-480 (2000).
[Nog04] G. Noguere et al., Int. Conf. on Nuclear Data for
Science and Technology, Santa Fe, USA (2004) and
Sixth EC Conf. on the management and disposal of
radioactive waste, EURADWASTE'04, Luxembourg (2004).
[Mox90] M.C. Moxon and J.B. Brisland,Technical Report Harwell
Laboratory, CBNM/ST/90-131/1 (1990).
[Rae74] J. Raedt et al., Phys. Rev. C9(1974)2391.
[Sza79] A. Szanto De Toledo et al., Nucl. Phys A230(1979)309.
CONTENTS
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