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14-Si- 28 IRK EVAL-MAY96 S.Tagesen, H.Vonach, A.Trkov
DIST-JAN09 20090105
----JEFF-311 MATERIAL 1425
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
******************************************************************
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- EFF-3.0 (DIST-NOV01)
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This evaluation is a combination of a new evaluation for files
3 and 33 for all MT numbers with the files 2, 4, 6, 12 and 14
from ENDF/B-VI.5 (see file 1 of ENDF/B-VI for 28Si). The new file
3 and 33 was derived in the following way: The cross sections
from the EFF-2 file (results of model calculations) and their
estimated covariances (see Table 1) are used as prior
information which is successively improved by adding
experimental data (see Table 2) and by applying Bayes' theorem
to obtain the posterior information. For this process the code
GLUCS was used. For some cross sections, not covered in EFF-2,
priors were taken from BROND and recent nuclear model
calculations. As results we obtained evaluated cross sections
and their covariances for a chosen set of 15 independent cross
sections in a group structure of 31 neutron energy groups 0.2
- 1 MeV wide. A final coupled set of evaluated cross sections
and covariances was obtained by a last GLUCS run including the
experimental data for redundant cross sections, that is all
cross sections which can be expressed as sums or differences
of the basic cross sections of Table 1. In this way evaluated
cross sections and covariances were obtained for the 15 basic
cross sections of Table 1 in a group structure of 31 neutron
energy groups.
The covariances obtained in this way are directly used as
corresponding files 33 in the new evaluation.
For the cross sections (file 3 data) a more detailed
description is needed in two respects. Cross section
fluctuations within the relatively large energy groups of the
GLUCS evaluation have to be included wherever sufficiently
well known and a number of the cross sections e.g.
n,n4-16, n,p have to be subdivided into their components, e.g.
the inelastic neutron scattering cross sections to the
individual levels No 4-16 according to the calculated cross
section ratios of the ENDF/B-VI.5 evaluation.
In detail the final MF3 file was derived from the described
GLUCS output (group cross section) in the following way for
the different reaction types:
- MT1: The fine structure observed in the most recent high-
resolution experiment [Larson 96] was superimposed on our
group cross sections.
- MT 51: The fine structure from ENDF/B-VI, which is based on
the data of [Dickens 74] was superimposed on our group cross
sections.
- MT52 and MT53: Our cross sections for MT 851 were split into
these two components according to the calculated cross
section ratios of ENDF/B-VI.5.
- MT 54-66: The cross sections for MT 852 were split in the
same way as MT 851.
- MT 103: The total (n,p) cross section was split into its
components for proton emission to discrete levels MT 600-613
and to the continuum MT 649 according to the cross section
ratios given in ENDF/B-VI.5. In addition the fine structure
used in ENDF/B-VI.5 was superimposed to the total and all
partial (n,p) cross sections below 9 MeV).
- MT 107: The total (n,p) cross section was split into its
components for proton emission to discrete levels MT 800-815
and to the continuum. In addition the fine structure used in
ENDF/B-VI.5 was superimposed to the total and all partial
(n,a) cross sections.
Though redundant, the total (n,p) and (n,a) cross sections (MT
103 and MT 107) are also given in the file for covenience.
Table 1: Choice of basic cross sections and priors for the
GLUCS evaluation of 28Si
Reaction Cross section Covariance matrix
total exp. Larson 96 exp. uncertainties
n,2n EFF 2.4 new estimate
n,na EFF 2.4 new estimate
n,np EFF 2.4 new estimate
n,n1 EFF 2.4 new estimate
n,n2-3 EFF 2.4 new estimate
n,n4-16 EFF 2.4 new estimate
n,n cont EFF 2.4 new estimate
n,g EFF 2.4 new estimate
n,p EFF 2.4 new estimate
n,d new GNASH calc. new estimate
n,t BROND new estimate
n,3He BROND new estimate
n,a EFF 2.4 new estimate
n,2p EFF 2.4 new estimate
Table 2: Experimental data used in the GLUCS evaluation for
cross sections and covariances
total (MT1): Foster 71, Schwartz 71, Perey 72, Carlson 67,
Larson 81, Finley 93, Cierjacks 68, Manero 70, Tsukada 63,
Cabe 73, Calvi 66, Fasoli 63, Martin 86, Grimes 69,
Weigmann 87, Larson 96.
n,n1 (MT 51): Perey 71, Sullivan 79, Lind 61, Petitt 66,
Drake 69, Haout 82, Martin 68, Boerker 88, Brandenberger 72,
Tanaka 70, Kinney 70, Obst 73, Velkley 74, Howell 88,
Baba 85, Kliczewski 78, Yamanonti 77, Alarcon 86, Olson 90,
Schmidt 00.
n,n2+3 (MT 851): Dickens 70, Drake 69, Haout 82, Kinney 70,
Schmidt 00, Tanaka 70.
n,n4-16 (MT 852): Takahashi 88.
n,p (MT 103): Paul 53, Mainsbridge 63, Marion 56, Robertson 73,
Cohen 56, Bahal 86, Anderson 63, Schantl 70, Ikeda 88,
Kawade 90, Pasquarelli 67, Mitra 66, Dresler 73, Nghoc 80,
Csikai 86, Shchebolev 77, Filatenkov 99, Mannhart 00,
Fessler 00, Ranakumar 68.
el (MT 2): Kinney 70, Petitt 66, Obst 73, Velkley 74, Clarke 64,
Drake 69, Howell 88, Alarcon 86, Tanaka 70, Martin 68,
Yamanouti 77, Olsson 87, Boerker 88, Kliczewski 78,
Brandenberger 73, Schmidt 00.
inel (MT 4): Dickens 74, Dickens 70, Lychagin 92, Benetskij 65,
Connell 75, Drosg 00, Abbondanno 73, Zong Ren 79,
Hongyu 94, Besotocnij 80, Drake 78.
n,a (MT 107): Anderson 63, Mainsbridge 63.
n,p prod (MT 103 + MT 28): Bateman 99.
n,a prod (MT 107 + MT 22): Bateman 99.
n,g (MT 102): Rigaud 70, Budnar 79.
non (MT 3): Flerov 56, Zhong 86.
References:
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(1953)
Cohen 56: A.V. Cohen and P.H. White, Nucl.Phys. 1, 73(1956)
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(USSR) 4, 617 (1956)
Marion 56: J.B. Marion et al., Phys.Rev. 101, 247 (1956)
Lind 61: D.A. Lind and R.B. Day, Ann.Phys. 12, 485 (1961)
Anderson 63: G. Anderson, Lindstrom, and E. Rossle,
Phys.Letters 5, 71 (1963)
Fasoli 63: U. Fasoli et al., Nuov.Cim. B44, 455 (1963)
Mainsbridge 63: B. Mainsbridge, T.W. Bonner, and T.A. Rabson,
Nucl.Phys. 48, 83 (1963)
Tsukada 63: K. Tsukada, private communication to EXFOR
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(1964)
Benetskij 65: Benetskij, Comptes rendu du Congres International
de Physique Nucleaire, Paris, 2 - 8 June 1964,
Vol. 2, 817 (1965)
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Abbondanno 73: U. Abbondanno et al., J.Nucl.En. 27, 227 (1973)
Cabe 73: J. Cabe and M. Cance, Report CEA-R-4524 (1973)
Dresler 73: J. Dresler, J. Araminowicz, and U. Garnska,
Report INR-1464 (1973)
Obst 73: A.W. Obst and J.L. Weil, Phys.Rev. C7, 1076 (1973)
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26, 71 (1975)
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54 (1977)
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Haout 82: G. Haout et al., Proc.Int.Conf. on Nucl.Data for
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Martin 86: P.W. Martin, private communication to EXFOR
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communication
Fessler 00: A. Fessler et al., Nucl.Sci.Eng. 134, 171 (2000)
Mannhart 00: W. Mannhart, private communication Sept. 2000,
to be published
Schmidt 00: D. Schmidt, private communication
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