24-Cr- 50
24-CR- 50 NEDAC EVAL-MAR87 T.ASAMI(NEDAC)
DIST-SEP89 REV2-SEP93
----JENDL-3.2 MATERIAL 2425
-----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 ********************
(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/.
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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. EVALUATION WAS 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 =
5.0 FM/9/.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRAL.
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
ELASTIC 2.31
CAPTURE 15.9 7.41
TOTAL 18.2
MF=3 NEUTRON CROSS SECTIONS
BELOW 300 KEV, ZERO BACKGROUND CROSS SECTION WAS GIVEN.
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, 51-55, 91 INELASTIC SCATTERING
CALCULATED WITH THE CASTHY CODE/10/, TAKING ACCOUNT OF THE
CONTRIBUTION FROM THE COMPETING PROCESSES AND USING THE
DISCRETE LEVEL DATA/11/ SHOWN BELOW. THE CONTRIBUTIONS FROM
THE DIRECT PROCESS FOR THE LEVEL MARKED WITH '*' WERE CALCULA-
TED WITH THE DWUCK CODE/12/. THE DEFORMATION PARAMETERS USED
IN THE CALCULATION WERE ASSUMED BASED ON PETERSON'S DATA/13/.
LEVEL ENERGY(MEV) SPIN-PARITY
G.S. 0.0 0+
1 0.7833 2+ *
2 1.8814 4+ *
3 2.9245 2+ *
4 3.1611 2+ *
5 3.1641 6+
6 3.3247 4+
7 3.5946 4+
8 3.6101 4+
9 3.6295 1+
10 3.6940 0+
11 3.6978 2+
12 3.7924 5+
13 3.8261 6+
14 3.8443 3+
15 3.8500 0+
16 3.8752 6+
17 3.8953 2+
18 3.8983 4+
19 3.9377 3+
20 4.0517 0+
LEVELS ABOVE 4.066 MEV WERE ASSUMED TO BE OVERLAPPING.
THE CALCULATED DATA FOR THE INELASTIC SCATTERING WERE FINALLY
LUMPED FOR THE CONVENIENCE ON THE CONSTRUCTION OF THE ELEMENTA
DATA AS FOLLOWS:
MT NO. LEVEL ENERGY(MEV) LUMPING OF LEVEL
51 0.7833 1
52 1.8814 2
53 2.9245 3
54 3.1611 4-5
55 3.3247 6
91 3.5946 OVER 7
FURTHERMORE, THE DATA OF MT=51 WERE MODIFIED BY CONSIDERING
EXPERIMENTAL DATA. THE TOTAL INELASTIC SCATTERING CROSS SEC-
TION (MT=4) IS THE SUM OF MT'S FROM 51 TO 91.
MT=16 (N,2N)
MAINLY BASED ON THE EXPERIMENTAL DATA OF BORMANN /14/.
MT=22 (N,NA)
CALCULATED WITH THE GNASH CODE/15/.
MT=28 (N,NP)
CALCULATED WITH THE GNASH CODE/15/.
MT=102 CAPTURE
CALCULATED WITH THE CASTHY CODE/10/ AND NORMALIZED TO
REPRODUCE THE ELEMENT DATA OF 10 MB AT 50 KEV.
MT=103 (N,P)
CALCULATED WITH THE GNASH CODE/15/.
MT=107 (N,A)
CALCULATED WITH THE GNASH CODE AND NORMALIZED AT 14.8 MEV IN
REFERRING TO GRIMES'S DATA/16/. THE DATA NEAR THE THRESHOLD
WERE MODIFIED IN REFERRING TO THE EXPERIMENTAL DATA FOR THE
ELEMENT CR(N,ALPHA)/17/.
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=16, 22, 28, 91 (N,2N), (N,NA), (N,NP), CONTINUUM INELASTIC
APPROXIMATELY TRANSFORMED FROM THE MF=6 DATA (DDX) OF JENDL
FUSION FILE.
MT=51-55 INELASTIC SCATTERING
CALCULATED WITH THE CASTHY CODE AND THE DWUCK CODE/12/.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16, 22, 28, 91
APPROXIMATELY TRANSFRMED 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) 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) DATA TAKEN FROM ENSDF(EVALUATED NUCLEAR STRUCTURE DATA FILE).
12) KUNZ P.D. : UNPUBLISHED.
13) PETERSON R.J. AND PERLMAN, D.E.: NUCL. PHYS. A117,185(1968).
14) BORMANN M. : THE DATA (1965) IN EXFOR FILE.
15) YOUNG P.G. AND ARTHUR E.D. : LA-6947 (1977).
16) GRIMES S.M. ET AL. : PHYS. REV. C19, 2127 (1979).
17) PAULSEN A. : NUCL. SCI. ENG. 78, 377 (1981).