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45-Rh-103 CAD,BRC,+ EVAL-FEB05 E.DUPONT, E.BAUGE, M.C.Moxon
DIST-JAN09 20090105
----JEFF-311 MATERIAL 4525
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 Updated **
** Modification: Modifications by E. Dupont **
******************************************************************
Modification of JEFF-3.1
========================------------------------------------------
2006-07 E.Dupont (CEA)
MF2/MT151 -Correction of a typo in GT (Gamma-Total)
for the resonance at energy ER=5.54855E+02
-set AWRI=AWR for LRU=1 (RRR)
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 104Rh
MF10/all -IZAP added
MF10/MT102 -Deleted (move to MF9)
***************************** JEFF-3.1 *************************
New evaluation
MAIN AUTHORS AND CONTRIBUTIONS
==============================------------------------------------
E. DUPONT, CEA-DEN/DER/SPRC (Cadarache, France)
Unresolved resonance region and continuum modelling, comparison
with experimental data, assembly and verification of the file,
preliminary integral tests (reactor applications).
E. BAUGE, CEA-DAM/DPTA/SPN (Bruyeres-le-Chatel, France)
Semi-microscopic deformed optical model potential and
coupled-channels calculations.
J.-Ch. SUBLET, CEA-DEN/DER/SPRC (Cadarache, France)
Processing and validation for activation applications.
+ A. BRUSEGAN, P. SCHILLEBEECKX, JRC-IRMM (Belgium)
E. BERTHOUMIEUX, CEA/DSM-Saclay (France)
M.C. MOXON (United Kingdom)
New measurements and analysis up to 1 keV of transmission
and capture experimental data.
+ 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
===================-----------------------------------------------
* Resolved Resonance Region (RRR) 1.E-05 eV < En < 4115.9 eV
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
E < 600 eV New parameters from the analysis of recent GELINA
transmission and capture measurements [Bru04,Mox04].
E > 600 eV Resonance parameters for Multi-Level Breit-Wigner
formula were adopted from ENDF/B-VI.8 [Cha99].
Calculated 2200 m/sec cross-sections and resonance integrals
are as follows:
| 2200 m/s values | Resonance Integral
| (barns) | (barns)
---------+-----------------+--------------------
Total | 146.63 | 1053.06
Elastic | 3.88 | 84.83
Capture | 142.75 | 968.23
* Unresolved Resonance Region (URR) 4115.9 eV < En < 40146 eV
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
New evaluation [Dup04] with the SAMMY/FITACS code [Lar03,Fro89].
The average resonance parameters were adjusted on averaged EXFOR
cross-section measurements [Exf03]:
- Total [Div68,Jai65,Smi84,Poe83]
- Capture [Fri71,Mac67,Wes60,Rig76,Wis90,Pop62,Bok91]
Average UR parameters (En=0)
| l=0 | l=1 | l=2
-------------+--------+--------+--------
R' (fm) | 6.51 | 6.54 | 6.54
(eV) | 26.00 | 11.97 | 7.59
Sl *10**4 | 0.58 | 4.21 | 0.63
(meV) | 172.00 | 160.00 | 172.00
Although these average parameters were adjusted on a broader
energy range, the unresolved resonance region upper limit is
set to the first inelastic threshold at 40.146 keV.
The SAMMY/FITACS Hauser-Feshbach average parameters have been
transformed into Single-Level Breit-Wigner average parameters
to comply with ENDF-6 format.
* Continuum Region (CONT) 40146 eV < En < 30 MeV
~~~~~~~~~~~~~~~~~~~~~~~~~
New evaluation [Dup04] based on model calculations using the
ECIS-97 [Ray94] and TALYS-0.52 [Kon04] codes with a semi-
microscopic deformed optical model potential [Bau01] for
neutrons and protons and folded OMPs -- derived from the default
nucleon potentials [Kon03] of TALYS -- for other particles
(deuterons, tritons, helions and alphas).
Nucleus deformation: Beta-2 = 0.1850 (Delta-2 = 1.0753 fm)
Beta-4 = 0.0044 (Delta-4 = 0.0256 fm)
Channels coupled in a vibrational model within the ECIS code are
indicated in the following 103Rh levels scheme [Fir98] that was
used in this work,
Coupled Spin- Energy
Channels parity (keV)
15 yes 9/2- _________________________________ 920.10
14 5/2- _________________________________ 880.47
13 yes 7/2- _________________________________ 847.58
12 13/2+ _________________________________ 821.46
11 1/2- _________________________________ 803.07
10 9/2+ _________________________________ 780.50
9 11/2+ _________________________________ 657.72
8 3/2+ _________________________________ 651.80
7 5/2+ _________________________________ 650.08
6 7/2+ _________________________________ 607.45
5 5/2+ _________________________________ 536.84
4 yes 5/2- _________________________________ 357.41
3 yes 3/2- _________________________________ 294.98
2 9/2+ _________________________________ 93.04
1 7/2+ _________________________________ 39.76
0 yes 1/2- _________________________________ 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) | 6.47 | 6.47 | 6.47
(eV) | 25.90 | 11.92 | 7.56
Sl *10**4 | 0.46 | 4.69 | 0.57
(meV) | 166.00 | 166.00 | 166.00
The model parameters were fine-tuned to enforce agreement with
experimental data [Exf03]:
- Differential cross-sections (including isomer productions)
(n,tot), (n,n), (n,n'), (n,ni), (n,2n), (n,3n), (n,g)
- Double-differential elastic scattering cross-sections
FILE INFORMATION
==================================================================
This file was formated thanks to SAMMY [Lar03] and TALYS [Kon04]
formatting capabilities.
MF= 1 -- General information
~~~~~~~~~~~~~~~~~~~~~~~~~~~~
MT=451 -> This descriptive data and directory
MF= 2 -- Resonance parameters
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
MT=151 -> Resolved and unresolved resonance parameters
Resolved resonance parameters : 1.0000-5 eV -- 4.1159+3 eV
MLBW parameters for s- and p-waves
Scattering radius AP = 6.56 fm
Unresolved resonance parameters : 4.1159+3 eV -- 4.0146+4 eV
SLBW average parameters up to l=2
All parameters are energy dependent
Scattering radius AP = 6.51 fm
MF= 3 -- Reaction cross-sections
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
MT= 1 -> Total cross-section
Coupled-channels optical model (OM) calculations with a semi-
microscopic deformed OMP [Bau01]. The very few available
parameters were fine-tuned to better match the experimental
data [Exf03].
MT= 2 -> Elastic scattering cross-section
Sum of the shape-elastic (optical model) and compound-elastic
(statistical model) scattering cross-sections.
MT= 4 -> Total inelastic scattering cross-section
Sum of MT51 to MT65 (discrete levels) plus MT91 (continuum).
MT= 11 -> (n,2nd) cross-section
MT= 16 -> (n,2n) cross-section
MT= 17 -> (n,3n) cross-section
MT= 22 -> (n,na) cross-section
MT= 24 -> (n,2na) cross-section
MT= 25 -> (n,3na) cross-section
MT= 28 -> (n,np) cross-section
MT= 29 -> (n,n2a) cross-section
MT= 32 -> (n,nd) cross-section
MT= 33 -> (n,nt) cross-section
MT= 34 -> (n,nh) cross-section
MT= 37 -> (n,4n) cross-section
MT= 41 -> (n,2np) cross-section
MT= 42 -> (n,3np) cross-section
MT= 44 -> (n,n2p) cross-section
MT= 45 -> (n,npa) cross-section
MT= 51- 65 -> (n,n') cross-section for 1st-15th excited state
MT= 91 -> (n,n') continuum cross-section
MT=102 -> (n,gamma) cross-section
MT=103 -> (n,p) cross-section
MT=104 -> (n,d) cross-section
MT=105 -> (n,t) cross-section
MT=106 -> (n,h) cross-section
MT=107 -> (n,a) cross-section
MT=108 -> (n,2a) cross-section
MT=111 -> (n,2p) cross-section
MT=112 -> (n,pa) cross-section
MT=115 -> (n,pd) cross-section
MT=116 -> (n,pt) cross-section
MT=117 -> (n,da) cross-section
MT=600-615 -> (n,p) cross-section for 0th-15th excited state
Obtained by mapping continuum (n,p) cross-section from
pre-equilibrium and compound model on discrete states.
MT=649 -> (n,p) continuum cross-section
MT=650-665 -> (n,d) cross-section for 0th-15th excited state
Obtained by mapping continuum (n,d) cross-section from
pre-equilibrium and compound model on discrete states.
MT=699 -> (n,d) continuum cross-section
MT=700-715 -> (n,t) cross-section for 0th-15th excited state
Obtained by mapping continuum (n,t) cross-section from
pre-equilibrium and compound model on discrete states.
MT=749 -> (n,t) continuum cross-section
MT=750-765 -> (n,h) cross-section for 0th-15th excited state
Obtained by mapping continuum (n,h) cross-section from
pre-equilibrium and compound model on discrete states.
MT=799 -> (n,h) continuum cross-section
MT=800-815 -> (n,a) cross-section for 0th-15th excited state
Obtained by mapping continuum (n,a) cross-section from
pre-equilibrium and compound model on discrete states.
MT=849 -> (n,a) continuum cross-section
MF= 4 -- Angular distributions of secondary particles
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
The versatility of MF6 for the storage of almost any secondary
distribution entails that we only use MF4 for the neutron
elastic scattering distribution.
MT= 2 -> Elastic angular distribution
The Legendre coefficients are given on a sufficiently precise
energy grid. They are a sum of calculated Legendre coefficients
for compound nucleus and shape-elastic scattering.
MF= 6 -- Product energy-angle distributions
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
In MF6 we store all secondary energy, angle, and energy-angle
distributions, as well as all residual and discrete + continuum
photon production cross-sections. We thus do not use MF12 to
MF15 for the photon production that accompanies each reaction.
MT= 16 -> (n,2n) energy-angle distr. and photon production
First, for each type of outgoing particle, the (trivial) integer
particle yields are given. Next, on a sufficiently dense
incident energy grid the secondary energy-angle distributions
are specified by means of the relative emission spectra and the
parameters for the Kalbach systematics for angular
distributions. Next, the photon yield is tabulated as a function
of incident energy. For each incident energy, the photon
production is given for all discrete gamma lines present in the
final nucleus. A continuum photon distribution is added to this.
We assume isotropy for all produced gamma rays.
The following MT-numbers follow the same procedure as for MT16
MT= 11 -> (n,2nd) energy-angle distr. and photon production
MT= 17 -> (n,3n) energy-angle distr. and photon production
MT= 22 -> (n,na) energy-angle distr. and photon production
MT= 24 -> (n,2na) energy-angle distr. and photon production
MT= 25 -> (n,3na) energy-angle distr. and photon production
MT= 28 -> (n,np) energy-angle distr. and photon production
MT= 29 -> (n,n2a) energy-angle distr. and photon production
MT= 32 -> (n,nd) energy-angle distr. and photon production
MT= 33 -> (n,nt) energy-angle distr. and photon production
MT= 34 -> (n,nh) energy-angle distr. and photon production
MT= 37 -> (n,4n) energy-angle distr. and photon production
MT= 41 -> (n,2np) energy-angle distr. and photon production
MT= 42 -> (n,3np) energy-angle distr. and photon production
MT= 44 -> (n,n2p) energy-angle distr. and photon production
MT= 45 -> (n,npa) energy-angle distr. and photon production
MT= 91 -> (n,n') cont. energy-angle distr. and photon prod.
MT=108 -> (n,2a) energy-angle distr. and photon production
MT=111 -> (n,2p) energy-angle distr. and photon production
MT=112 -> (n,pa) energy-angle distr. and photon production
MT=115 -> (n,pd) energy-angle distr. and photon production
MT=116 -> (n,pt) energy-angle distr. and photon production
MT=117 -> (n,da) energy-angle distr. and photon production
MT=649 -> (n,p) cont. energy-angle distr. and photon prod.
MT=699 -> (n,d) cont. energy-angle distr. and photon prod.
MT=749 -> (n,t) cont. energy-angle distr. and photon prod.
MT=799 -> (n,h) cont. energy-angle distr. and photon prod.
MT=849 -> (n,a) cont. energy-angle distr. and photon prod.
MT= 51 -> (n,n') angular distribution and photon production
for first excited state
The angular distributions for inelastic scattering to the
discrete inelastic levels is given with Legendre coefficients.
The following MT-numbers follow the same procedure as for MT51
MT= 52- 65 -> (n,n') angular distribution and photon production
for 2nd-15th excited state
MT=600-615 -> (n,p) angular distribution and photon production
for 0th-15th excited state
MT=650-665 -> (n,d) angular distribution and photon production
for 0th-15th excited state
MT=700-715 -> (n,t) angular distribution and photon production
for 0th-15th excited state
MT=750-765 -> (n,h) angular distribution and photon production
for 0th-15th excited state
MT=800-815 -> (n,a) angular distribution and photon production
for 0th-15th excited state
MF= 8 -- Radioactive nuclide production
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
For reactions to isomers, MF8 designates where the information
for isomeric versus ground state production can be found, i.e.
for each MT number it points to either MF6, MF9 or MF10.
MF= 9 -- Multiplicities for production of radioactive nuclides
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
MT=102 -> (n,gamma) yields to ground state and isomer
MF=10 -- Cross-sections for production of radioactive nuclides
~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
MT= 4 -> (n,n') cross-section to ground state and isomer
MT= 16 -> (n,2n) cross-section to ground state and isomer
MT= 17 -> (n,3n) cross-section to ground state and isomer
MT= 22 -> (n,na) cross-section to ground state and isomer
MT= 25 -> (n,3na) cross-section to ground state and isomer
MT= 29 -> (n,n2a) cross-section to ground state and isomer
MT= 37 -> (n,4n) cross-section to ground state and isomer
MT=111 -> (n,2p) cross-section to ground state and isomer
FILE CHECKING AND PROCESSING
============================--------------------------------------
This file has been checked successfully by the ENDF utility codes
CHECKR, FIZCON [Dun02] and has been processed successfully by the
NJOY-99.90 [McF00] and PREPRO-2000 [Cul00] processing codes.
REFERENCES
==========--------------------------------------------------------
[Bau01] E. Bauge, et al., Phys. Rev. C63, 024607 (2001).
[Bok91] M.V. Bokhovko, et al., Average fast neutron radiative
capture cross sections for fission products and for
isotopes of rare earth elements, in Int. Conf. on Nuclear
Data for Science and Technology, 62-64, Juelich, Germany,
May 1991, Exfor #41148.
[Bru04] A. Brusegan, et al., in Int. Conf. on Nuclear Data for
Science and Technology, Santa Fe, USA, September 2004.
[Cha99] J.H. Chang, S.F. Mughabghab, August 1999.
[Cul00] D.E. Cullen, PREPRO2000 - ENDF/B Pre-processing Codes,
IAEA-NDS-39 rev.10 (2000).
[Div68] M. Divadeenam, Strength functions and the optical model,
Dissertation Abstracts DA/B 28, 3834, March 1968,
Exfor #10523.
[Dun02] C.L. Dunford, ENDF Utility Codes Release 6.13, BNL, 2002.
[Dup04] E. Dupont, et al., in Int. Conf. on Nuclear Data for
Science and Technology, Santa Fe, USA, September 2004.
[Exf03] Nuclear Reaction Data Centres Network (NRDC, IAEA),
OECD NEA Data Bank EXFOR retrieval system (2003),
see http://www.nea.fr/html/dbdata/x4/.
[Fir98] R.B. Firestone, Table of Isotopes, 8th Edition (1998).
[Fri71] M. Fricke, A. Carlson, The rhodium neutron-capture cross
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Nuclear Society, vol. 14, 352, June 1971, Exfor #10211.
[Fro89] F. Froehner, Nucl. Sci. Eng. 103, 119-128 (1989).
[Jai65] A.P. Jain, et al., Optical-Model Interpretation of
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Phys. Rev. B137, 83-89, January 1965, Exfor #11904.
[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, "Updated Users' Guide for SAMMY: Multilevel
R-Matrix Fits to Neutron Data Using Bayes' Equations",
ORNL/TM-9179/R6, July 2003.
[Mac67] R.L. Macklin, J.H. Gibbons, Capture-cross-section studies
for 30-220 keV neutrons using a new technique, Phys. Rev.
159, 1007, 1967, Exfor #11679.
[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).
[Mox04] M.C. Moxon, private communication (October 2004).
[Poe83] W.P. Poenitz, J.F. Whalen, Neutron total cross section
measurements in the energy region from 47 keV to 20 MeV,
ANL report, ANL/NDM-80, May 1983, Exfor #12853.
[Pop62] JU.P. Popov, F.L. Shapiro, Energy dependence of cross
sections for (n,gamma) reactions on a number of odd-Z
nuclei, Journal of Experimental and Theoretical Physics,
JET 15, 683, 1962, Exfor #40797.
[Ray94] J. Raynal, Notes on ECIS94, CEA Report CEA-N-2772 (1994).
[Rig76] C. le Rigoleur, et al., Absolute measurements of neutron
radiative capture cross-sections for Na-23,Cr,Mn-55,Fe,
Ni,Rh-103,Ta,Au-197,U-238 in the range 10 to 600 keV,
CEA report, CEA-R-4788, October 1976, Exfor #20572.
[Smi84] A.B. Smith, et al., The optical model of few-MeV neutron
elastic scattering from Z= 39 to 51 targets, Nucl. Phys.
A415, 1-29, March 1984, Exfor #12796.
[Wes60] L.W. Weston, et al., Neutron capture cross sections in
the keV region - Part II - spin orbit coupling and the
optical model, Annals of Physics, vol. 10, 477, 1960,
Exfor #11818.
[Wis90] K. Wisshak, et al., Measurements of keV neutron capture
cross sections with a 4-pi barium fluoride detector:
examples of 93-Nb, 103-Rh and 181-Ta, Phys. Rev. C42,
1731, October 1990, Exfor #22195.
CONTENTS
========----------------------------------------------------------
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