27-CO- 59 KHI EVAL-AUG88 T.WATANABE
DIST-SEP89 REV2-APR94
----JENDL-3.2 MATERIAL 2725
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-08 NEWLY EVALUATED BY T.WATANABE
(KAWASAKI HEAVY INDUSTRIES, LTD.)
94-04 JENDL-3.2.
GAMMA PRODCTION DATA EVALUATED BY T.ASAMI (DATA ENG.)
OTHER DATA WERE MAINLY ADOPTED FROM JENDL FUSION FILE.
COMPILED BY T.NAKAGAWA
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(3,4), (3,51-91), (4,16-91), (5,16-91)
ADOPTED FROM JENDL FUSION FILE
(3,102)
(3,2) TO COMPENSATE THE ABOVE CROSS SECTION CHANGES
GAMMA-RAY PRODUCTION DATA: NEW EVALUATION
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /1/ (AS OF NOV. 1993)
EVALUATED BY B.YU (CIAE) AND S.CHIBA (NDC/JAERI)
COMPILED BY B.YU .
CROSS SECTIONS WERE MAINLY TAKEN FROM JENDL-3.1 EXCEPT
FOR THE (N,N') (MT=51 TO 91) REACTIONS WHICH WERE TAKEN FROM
NEW CALCULATION WITH SINCROS-II/2/. ENERGY DISTRIBUTIONS
FOR MT=16, 22, 28 AND 91 WERE REPLACED BY THE SINCROS-II
CALCULATION. DDX (MF=6) WERE CREATED WITH F15TOB PROGRAM
/1/ IN WHICH MODIFIED KUMABE'S SYSTEMATICS /3/ WAS USED.
THE RATIO OF PRECOMPOUND TO COMPOUND 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/4/.
-------------------------------------------------------------
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MF=2
MT=151 RESONANCE PARAMETERS : 1.0E-5 EV - 100 KEV
RESOLVED RESONANCES FOR MLBW FORMULA:
PARAMETERS WERE EVALUATED BASED ON EXPERIMENTAL DATA
/5,6,7/ AND MODIFIED TO REPRODUCE EXPERIMENTAL TOTAL
CROSS SECTIONS. NEGATIVE ENERGY LEVELS WERE ADDED TO
REPRODUCE 2200 M/S TOTAL AND CAPTURE CROSS SECTIONS.
CALCULATED 2200 M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/SEC RES. INTEG.
ELASTIC 6.0 B -
CAPTURE 37.18 B 75.6 B
TOTAL 43.19 B -
MF=3 NEUTRON CROSS SECTIONS : ABOVE 100 KEV
MT=1 TOTAL
UP TO 4 MEV, BASED ON EXPERIMENTAL DATA /8,9/. ABOVE 4 MEV,
TOTAL CROSS SECTION WAS CALCULATED WITH OPTICAL AND
STATISTICAL MODEL CODE CASTHY/10/.
THE SPHERICAL OPTICAL POTENTIAL PARAMETERS WERE EVALUATED TO
REPRODUCE EXPERIMENTAL TOTAL CROSS SECTIONS /8,11/.
V = 49.65 - 0.114*EN MEV R0= 1.241 FM A0= 0.533 FM
WS= 8.625-0.05306*EN MEV RS= 1.421 FM B = 0.292 FM
VSO= 7.724 MEV RSO=1.151 FM ASO=0.7 FM
MT=2 ELASTC SCATTERING
TOTAL CROSS SECTION - SUM OF PARTIAL CROSS SECTIONS
MT= 4, 51 - 70, 91 INELASTIC SCATTERING
TAKEN FROM JENDL FUSION FILE. THE LEVEL SCHEME WAS TAKEN FROM
REF./4/ CONTRIBUTIONS OF THE DIRECT PROCESS WAS CALCULATED
FOR THE LEVELS MARKED WITH '*'.
NO. ENERGY(MEV) SPIN-PARITY (DIRECT PROCESS)
G.S 0.0 7/2-
1 1.0993 3/2- *
2 1.1905 9/2- *
3 1.2920 3/2- *
4 1.4343 1/2-
5 1.4595 11/2- *
6 1.4820 5/2- *
7 1.7450 7/2- *
8 2.0630 5/2- *
9 2.0880 7/2- *
10 2.1460 7/2-
11 2.1533 15/2-
12 2.183 5/2-
13 2.205 5/2- *
14 2.3971 9/2-
15 2.479 7/2-
16 2.537 9/2-
17 2.5405 3/2-
18 2.5816 9/2+
19 2.584 5/2-
20 4.0 5/2- *
LEVELS ABOVE 2.584 MEV WERE ASSUMED TO BE OVERLAPPING.
MT=16 (N,2N)
BASED ON EXPERIMENTAL DATA /12,13,14,15/ AND YAMAMURO'S
THEORETICAL CALCULATIONS /16/.
MT=22,28,104 (N,N ALPHA),(N,NP),(N,D)
YAMAMURO'S EVALUATION WAS ADOPTED /16/.
MT=102 CAPTURE
STATISTICAL MODEL CALCULATION WITH CASTHY CODE /10/ WAS
PERFORMED. ABOVE 800 KEV, EYE-GUIDED CURVE TO THE EXPERIMENTAL
DATA /6,17,18,19/.
MT=103 (N,P)
BASED ON EXPERIMENTAL DATA /12,20,21,22/.
MT=107 (N,ALPHA)
JENDL-2 DATA WERE ADOPTED WITH SLIGHT MODIFICATION BASED ON
EVAIN'S EVALUATION /23/ AND EXPERIMENTAL DATA /12,24/.
MT=251 MU-BAR
CALCULATED FROM THE DATA IN MF=4.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
OPTICAL MODEL CALCULATION.
MT=16,22,28,51-70,91
ADOPTED FROM JENDL FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,22,28,91
ADOPTED FROM JENDL FUSION FILE.
MF=12 GAMMA-RAY PRODUCTION MUTIPLICITIES AND TRANSITION
PROBABILITIES
MT=16,22,28,91,103,104,107
MULTIPLICITIES WERE CALCULATED WITH GNASH /25/
MT=51-68
TRANSITION PROBABILITIES WERE GIVEN.
MT=102
FROM ENERGY BALANCE.
MF=14 GAMMA-RAY ANGULAR DISTRIBUTIONS
MT=16,22,28,51-68,91,102,103,104,107
ISOTROPIC DISTRIBUTIONS WERE ASSUMED.
MF=15 GAMMA-RAY ENERGY DISTRIBUTIONS
MT=16,22,28,91,103,104,107
CALCULATED WITH GNASH /25/
MT=102
CALCULATED WITH CASTHY /10/ AT THERMAL ENERGY AND WITH GNASH
ABOVE 100 KEV.
REFERENCES
1) CHIBA, S. ET AL.: JAERI-M 92-027, P.35 (1992).
2) YAMAMURO, N.: JAERI-M 90-006 (1990).
3) KUMABE, I. ET AL.: NUCL. SCI. ENG., 104, 280 (1990).
4) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDC.
5) GARG J.B. ET AL.: NUCL. SCI. ENG. 65,76 (1978).
6) SPENCER R.R. AND MACKLIN, R.L.: NUCL.SCI.ENG. 61,346 (1976).
7) MUGHABGHAB S.F. ET AL.:"NEUTRON CROSS SECTIONS VOL.1 PART A",
ACADEMIC PRESS (1981).
8) FOSTER,JR. D.G. AND GLASGOW D.W.: PHYS. REV. C3, 576 (1973).
9) HARVEY J.A.: TAKEN FROM EXFOR (1986).
10) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
11) CIERJACKS S.: KFK-1000 (1969).
12) IKEDA Y. ET AL.: JAERI 1312 (1988).
13) HASAN S.J. ET AL.: PROC. INT. CONF. NUCLEAR DATA FOR BASIC
AND APPLIED SCIENCE, SANTA FE, 1985, P.155 (1986).
14) HUANG JIAN-ZHOU ET AL.: CHINESE NUCL. PHYS. 3,59 (1981).
15) VEESER L.R. ET AL.: PHYS. REV. C16, 1792 (1977).
16) YAMAMURO N.: PRIVATE COMMUNICATION.
17) PAULSEN A.: Z. PHYS. 205, 226 (1967).
18) RIGAUD F. ET AL.: NUCL. PHYS. A273, 551 (1971).
19) BUDNAR M. ET AL.: INDC(YUG)-6 (1979).
20) SMITH D.L. ET AL.: NUCL. SCI. ENG. 58, 314 (1975).
21) WILLIAMS J.R. AND ALFORD, W.L.: PROC. INT. CONF. NUCLEAR DATA
FOR BASIC AND APPLIED SCIENCE, SANTA FE, 1985, P.215 (1986).
22) HASAN S.J. ET AL.: J. PHYS. G12, 397 (1986).
23) EVAIN B.P. ET AL.: ANL/NDM-89 (1985).
24) MEADOWS J.W. ET AL.: ANN. NUCL. ENERGY 14, 603 (1987).
25) YOUNG P.G. AND ARTHUR E.D.: LA-6974 (1977).