24-CR- 52 NEDAC EVAL-MAR87 T.ASAMI(NEDAC)
DIST-SEP89 REV2-SEP93
----JENDL-3.2 MATERIAL 2431
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 NEW EVALUATION WAS MADE BY T.ASAMI.
88-12 MF/MT=3/107 MODIFIED.
93-09 JENDL-3.2.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(3,2)
(3,4), (3,91) TAKEN FROM JENDL FUSION FILE
(3,66-67) DELETED
(4,16-28), (4,91) TAKEN FROM JENDL FUSION FILE
(5,16-91) TAKEN FROM JENDL FUSION FILE
***********************************************************
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JENDL FUSION FILE /1/ (AS OF SEP. 1993)
EVALUATED B.YU (CIAE) AND S.CHIBA (NDC/JAERI)
COMPILED BY B.YU.
CROSS SECTIONS WERE MAINLY TAKEN FROM JENDL-3. THE
(N,N') CONTINUUM CROSS SECTION (MT=91) IN THE WHOLE ENERGY
REGION AND ITS SPECTRA WERE TAKEN FROM THE SINCROS-II/2/
CALCULATION. SEVERAL DISCRETE LEVEL SCATTERING CROSS
SECTIONS (MT=63, 64, 65, 66) AND THEIR ANGULAR DISTRIBU-
TION WERE DELETED BECAUSE THEY WERE INCLUDED IN THE NEW
CONTINUUM INELASTIC SCATTERING CROSS SECTION(MT=91) TAKEN
FROM THE SINCROS-II CALCULATION. THE THRESHOLD OF MT=91
WAS CHANGED FROM 4.65 MEV TO 3.8 MEV. MF=6 OF MT=16, 22,
28 AND 91 WERE CREATED BY F15TOB PROGRAM/1/. MODIFIED-
KUMABE'S SYSTEMATICS/1/ WAS USED. THE PRECOMPOUND/COM-
POUND RATIO WAS TAKEN FROM THE SINCROS-II CALCULATION.
OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED
IN THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./2/.
LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/3/.
-------------------------------------------------------------
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCE PARAMETERS
RESOLVED PARAMETERS FOR MLBW FORMULA WERE GIVEN IN THE ENERGY
REGION FROM 1.0E-5 EV TO 300 KEV. EVALUATED MAINLY BASED ON
THE EXPERIMENTAL DATA OF STIEGLITZ+ 71/4/, BEER+74/5/,
ALLEN+77/6/, KENNY+77/7/, AGRAWAL+84/8/ AND BRUSEGAN+86/9/.
EFFECTIVE SCATTERING RADIUS = 5.2 FM /10/
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRAL
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
ELASTIC 2.96
CAPTURE 0.76 0.46
TOTAL 3.72
MF=3 NEUTRON CROSS SECTIONS
BELOW 300 KEV, ZERO BACKGROUND CROSS SECTION WAS GIVEN.
ABOVE 300 KEV, THE TOTAL AND PARTIAL CROSS SECTIONS WERE GIVEN
POINTWISE.
MT=1 TOTAL
OPTICAL AND STATISTICAL MODEL CALCULATION WAS MADE WITH
THE CASTHY CODE/11/. THE OPTICAL POTENTIAL PARAMETERS USED ARE
V = 46.78 - 0.262*EN, VSO = 7.0 (MEV)
WS = 4.87 + 0.352*EN, WV = 0 (MEV)
R = 1.30, RS = 1.40, RSO = 1.30 (FM)
A = 0.55, B = 0.40, ASO = 0.48 (FM)
SURFACE IMAGINARY PART IS IN DERIVATIVE WOODS-SAXON FORM.
MT=2 ELASTIC SCATTERING
OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS
FROM THE TOTAL CROSS SECTION.
MT=4, 51-62, 91 INELASTIC SCATTERING
CALCULATED WITH THE CASTHY CODE/11/, TAKING ACCOUNT OF THE
CONTRIBUTION FROM THE COMPETING PROCESSES AND USING THE
DISCRETE LEVEL DATA/12/ SHOWN BELOW. THE CONTRIBUTIONS FROM
THE DIRECT PROCESS FOR THE LEVELS MARKED WITH '*' WERE
CALCULATED WITH THE DWUCK CODE/13/. THE DEFORMATION PARAMETERS
USED IN THE CALCULATION WERE ASSUMED BASED ON A WEAK COUPLING
MODEL.
LEVEL ENERGY(MEV) SPIN-PARITY
G.S. 0.0 0+
1 1.4341 2+ *
2 2.3696 4+ *
3 2.6470 0+
4 2.7677 4+
5 2.9648 2+ *
6 3.1138 6+ *
7 3.1617 2+ *
8 3.4152 4+
9 3.4722 3+
10 3.6158 5+
11 3.7000 2+
12 3.7717 2+
13 3.9460 4+
14 3.9512 1+
15 4.0154 5+
16 4.0380 4+
17 4.5630 3- *
18 4.6270 5+
19 4.7060 2+
20 4.7410 2+
21 4.7507 8+
22 4.7940 0+
23 4.8045 6+
LEVELS ABOVE 4.816 MEV WERE ASSUMED TO BE OVERLAPPING.
THE CALCULATED DATA FOR THE INELASTIC SCATTERING WERE FINALLY
LUMPED FOR THE CONVENIENCE ON THE CONSTRUCTION OF THE ELEMENT
DATA AS FOLLOWS:
MT NO. LEVEL ENERGY(MEV) LUMPING
51 1.4341 1
52 2.3696 2
53 2.6470 3
54 2.7677 4
55 2.9648 5
56 3.1138 6
57 3.1617 7
58 3.4152 8
59 3.4722 9
60 3.6158 10
61 3.7000 11
62 3.7717 12
63 3.9460 13-14
64 4.0154 15-16
65 4.5630 17
66 4.6270 18
91 4.7060 OVER 19
THE DATA OF MT=51 AND 52 WERE MODIFIED BY CONSIDERING EXPERI-
MENTAL DATA. THE TOTAL INELASTIC SCATTERING CROSS SECTION
(MT=4) IS THE SUM OF MT'S FROM 51 TO 91. FOR JENDL-3.2, CROSS
SECTIONS OF MT'S FROM 63 TO 66 WERE INCLUDED INTO MT=91.
Q-VALUE OF MT=91 WAS CHANGED TO 3.8 MEV.
MT=16 (N,2N)
ADOPTED WERE THE EVALUATED DATA IN JENDL-2 WHICH HAVE BEEN
EVALUATED BASED ON THE EXPERIMENTAL DATA OF WENUSCH+62/14/,
BORMANN+68/15/, MASLOV+72/16/, QAIM72/17/, SAILER+77/18/ AND
GHORAI+87/19/.
MT=22 (N,NA)
CALCULATED WITH THE GNASH CODE/20/ AND NORMALIZED.
MT=28 (N,NP)
CALCULATED WITH THE GNASH CODE/20/ AND NORMALIZED.
MT=102 CAPTURE
CALCULATED WITH THE CASTHY CODE/11/ AND NORMALIZED TO 28.5 MB
AT 50 KEV SO AS TO REPRODUCE THE ELEMENT DATA OF 10 MB.
MT=103 (N,P)
CALCULATED WITH THE GNASH CODE/20/ AND NORMALIZED AT 14.8 MEV
TO THE RECOMMENDED VALUE OF FORREST/21/.
MT=107 (N,A)
CALCULATED WITH THE GNASH CODE AND NORMALIZED AT 14.8 MEV TO
THE AVERAGE VALUES OF THE EXPERIMENTAL DATA/22,23/. THE DATA
WERE MODIFIED NEAR THE THRESHOLD IN REFERRING TO THE THE
EXPERIMENTAL DATA OF PAULSEN /24/ FOR THE ELEMENT CR(N,A).
MT=251 MU-BAR
CALCULATED WITH OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 ELASTIC SCATTERING
CALCULATED WITH THE CASTHY CODE/11/.
MT=51-62 INELASTIC SCATTERING
CALCULATED WITH THE CASTHY CODE/11/ AND THE DWUCK CODE/13/.
MT=16, 22, 28, 91 (N,2N), (N,NA), (N,NP), CONTINUUM INELASTIC
APPROXIMATELY TRANSFORMED FROM THE MF=6 DATA (DDX) OF JENDL
FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16, 22, 28, 91
APPROXIMATELY TRANSFORMED FROM THE MF=6 DATA (DDX) OF JENDL
FUSION FILE.
REFERENCES
1) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).
2) YAMAMURO N.: JAERI-M 90-006 (1990).
3) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDC.
4) STIEGLIZ R.G. ET AL.: NUCL. PHYS. A163, 592 (1971).
5) BEER H. AND SPENCER R.P.: KFK-2063 (1974), ALSO NUCL. PHYS.
A240, 29 (1975).
6) ALLEN B.J. AND MUSGROVE A.R.DE L.: NEUTRON DATA OF STRUCTURAL
MATERIALS FOR FBR, 1977 GEEL MEETING, P.447, PERGAMON PRESS
(1979).
7) KENNY M.J. ET AL.: AAEC/E-400 (1977).
8) AGRAWAL H.M. ET AL.: PHYS. REV. C30, 1880 (1984).
9) BRUSEGAN A. ET AL.: 85SANTA FE VOL.1 P.633 (1986).
10) MUGHABGHAB S.F. ET AL.: "NEUTRON CROSS SECTIONS", VOL.1,
PART A (1981).
11) IGARASI S. AND FUKAFORI T.: JAERI 1321 (1991).
12) DATA TAKEN FROM ENSDF(EVALUATED NUCLEAR STRUCTURE DATA FILE).
13) KUNZ P.D.: UNPUBLISHED.
14) WENUSCH R. ET AL.: OSA 99, 1 (1962).
15) BORMANN M. ET AL.: NUCL. PHYS. A115, 309 (1968).
16) MASLOV G.N. ET AL.: NUCL. CONST. VOL.9, 50 (1972).
17) QAIM S.M.: NUCL. PHYS. A185, 614 (1972).
18) SAILER K. ET AL.: 1977 KIEV CONF. VOL.1, 246 (1977).
19) GHORAI S.K. ET AL.: J. PHYS. G13, 405 (1987).
20) YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).
21) FORREST R.A.: AERE-R-12419 (1986).
22) GRIMES S.M. ET AL.: PHYS. REV. C19, 2127 (1979).
23) DOLJA G.D. ET AL.: 1973 KIEV CONF. VOL.3, 131 (1973).
24) PAULSEN A.: NUCL. SCI. ENG. 78, 377 (1981).