24-Cr- 54
24-CR- 54 NEDAC EVAL-MAR87 T.ASAMI(NEDAC)
DIST-SEP89 REV2-SEP93
----JENDL-3.2 MATERIAL 2437
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 NEW EVALUATION WAS MADE FOR JENDL-3.
93-09 JENDL-3.2.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(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.
ALL OF CROSS SECTIONS WERE TAKEN FROM JENDL-3. MF=6 OF
MT=16, 22, 28 AND 91 WERE CREATED WITH SINCROS-II /2/ AND
F15TOB/1/ PROGRAM. MODIFIED-KUMABE'S SYSTEMATICS /1/ WAS
USED. THE PRECOMPOUND/COMPOUND RATIO WAS CALCULATED BY
THE SINCROS-II CODE SYSTEM.
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 BASED ON THE
EXPERIMENTAL DATA OF STIEGLITZ+71/4/, BEER+74/5/, ALLEN+77/6/,
KENNY+77/7/ AND BRUSEGAN+86/8/. EFFECTIVE SCATTERING RADIUS =
5.3 FM/9/.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRAL.
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
ELASTIC 2.54
CAPTURE 0.36 0.18
TOTAL 2.90
MF=3 NEUTRON CROSS SECTIONS
BELOW 300 KEV, NO 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/10/. 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, 51-60, 91 INELASTIC SCATTERING
CALCULATED WITH THE CASTHY CODE/10/, TAKING ACCOUNT OF THE
CON- TRIBUTION FROM THE COMPETING PROCESSES AND USING THE
DISCRETE LEVEL DATA/3/ SHOWN BELOW. THE CONTRIBUTIONS FROM
THE DIRECT PROCESS FOR THE LEVELS MARKED WITH '*' WERE CALCU-
LATED WITH THE DWUCK CODE/11/. 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 0.8349 2+ *
2 1.8237 4+ *
3 2.6195 2+ *
4 2.8294 0+ *
5 3.0739 2+ *
6 3.1600 2+ *
7 3.2225 6+
8 3.3920 1+
9 3.4366 2+
10 3.4680 1+
11 3.5140 2+
12 3.6552 4+
13 3.7198 2+
14 3.7858 4+
15 3.7989 4+
16 3.8640 2+
17 3.9340 1+
18 3.9900 3+
19 4.0160 0+
20 4.0450 6+
21 4.0832 4+
LEVELS ABOVE 4.088 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 0.8349 1
52 1.8237 2
53 2.6195 3
54 2.8294 4
55 3.0739 5
56 3.1600 6
57 3.2225 7
58 3.3920 8
59 3.4366 9
60 3.4680 10
91 3.5140 OVER 11
MT=16 (N,2N)
CALCULATED WITH THE GNASH CODE/12/.
MT=22 (N,NA)
CALCULATED WITH THE GNASH CODE AND NORMALIZED.
MT=28 (N,NP)
CALCULATED WITH THE GNASH CODE AND NORMALIZED.
MT=102 CAPTURE
CALCULATED WITH THE CASTHY CODE/10/ AND NORMALIZED AT 50 KEV
SO AS TO REPRODUCE THE ELEMENT DATA OF 10 MB.
MT=103 (N,P)
CALCULATED WITH THE GNASH CODE/12/ AND NORMALIZED AT 14.7 MEV
TO AN AVERAGE VALUE OF THE EXPERIMENTAL DATA/13,14,15/.
MT=107 (N,A)
CALCULATED WITH THE GNASH CODE AND NORMALIZED AT 14.8 MEV
TO AN AVERAGE VALUE OF THE EXPERIMENTAL DATA/14,15,16/.
MT=251 MU-BAR
CALCULATED WITH OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 ELASTIC SCATTERING
CALCULATED WITH THE CASTHY CODE/10/.
MT=51-60 INELASTIC SCATTERING
CALCULATED WITH THE CASTHY CODE AND THE DWUCK CODE/11/.
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) DATA TAKEN FROM ENSDF(EVALUATED NUCLEAR STRUCTURE DATA FILE).
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) BRUSEGAN A. ET AL.: 85SANTA FE VOL.1 P.633 (1986).
9) MUGHABGHAB S.F. ET AL.: "NEUTRON CROSS SECTIONS ", VOL.1, PART
A (1981).
10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
11) KUNZ P.D.: UNPUBLISHED.
12) YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).
13) VALKONEN M.: TAKEN FROM EXFOR (1976).
14) HUSAIN L. ET AL.: J. INORG. NUCL. CHEM. 29, 2665 (1967).
15) QAIM S.M. ET AL.: NUCL. PHYS. A283, 269 (1977).
16) SAILER K. ET AL.: 1977 KIEV CONF. VOL.1, 246 (1977).