22-TI- 0 KUR EVAL-SEP88 K.KOBAYASHI(KUR),H.HASHIKURA(TOK)
DIST-SEP89 REV2-FEB94
----JENDL-3.2 MATERIAL 2200
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
88-09 COMPILED BY T.ASAMI(NEDAC)
94-02 JENDL-3.2
DATA WERE MAINLY ADOPTED FROM JENDL FUSION FILE.
GAMMA-RAY PRODUCTION DATA WERE REVISED BY T.ASAMI(DATA ENG.)
COMPILED BY T.NAKAGAWA
***** MODIFIED PARTS FOR JENDL-3.2 ********************
ALL CROSS SECTIONS EXCEPT (3,1), (3,102) AND (3,107)
ALL ANGULAR DISTRIBUTIONS EXCEPT FOR (4,2).
ALL ENERGY DISTRIBUTIONS.
(12,102), (13,4), (15,102)
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /1/ (AS OF FEB. 1994)
EVALUATED BY K.KOSAKO (NEDAC) AND S. CHIBA (NDC/JAERI)
COMPILED BY K.KOSAKO.
- THE INELASTIC SCATTERING CROSS SECTIONS AND ANGULAR
DISTRIBUTIONS OF INELASTICALLY SCATTERED NEUTRONS (EXCEPT
CONTINUUM INELASTIC) WERE CALCULATED WITH CASTHY2Y AND
DWUCKY IN SINCROS-II SYSTEM/2/ INCLUDING CONTRIBUTIONS
FROM DIRECT REACTIONS.
- THE (N,2N), (N,NA), (N,NP) AND (N,P) REACTION CROSS
SECTIONS (MT=16, 22, 28, 103) WERE CALCULATED BY EGNASH2
IN THE SINCROS-II.
- ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS WERE REPLACED
BY THOSE CALCULATED BY EGNASH2. THE DDX'S OF THE
CONTINUUM NEUTRONS WERE CALCULATED BY KUMABE'S SYSTEMA-
TICS /3/ USING F15TOB /1/. THE PRECOMPOUND/COMPOUND
RATIO WAS CALCULATED BY THE SINCROS-II CODE SYSTEM.
- THE RESONANCE PARAMETERS, TOTAL, CAPTURE AND (N,A) CROSS
SECTIONS AND ANG. DISTRIBUTIONS OF ELASTICALLY SCATTERED
NEUTRONS WERE TAKEN FROM JENDL-3.1.
- 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 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCE PARAMETERS
RESOLVED PARAMETERS FOR MLBW FORMULA WERE GIVEN IN THE ENERGY
REGION FROM 1.0E-5 EV TO 100 KEV. PARAMETERS WERE CONSTRUCTED
WITH THE EVALUATED DATA FOR TI-46, -47, -48, -49 AND -50 OF TI
STABLE ISOTOPES, CONSIDERING THEIR ABUNDANCES IN THE TI
ELEMENT. THE ABUNDANCE DATA WERE TAKEN FROM REF./5/.
2200 M/S CROSS SECTION(B) RES. INTEGRAL(B)
ELASTIC 4.087
CAPTURE 6.092 2.92
TOTAL 10.18
MF=3 NEUTRON CROSS SECTIONS
BELOW 100 KEV, NO BACKGROUND CROSS SECTION WAS GIVEN.
ALL THE CROSS-SECTION DATA WERE DEDUCED FROM THE EVALUATED ONES
FOR FIVE STABLE ISOTOPES OF TI CONSIDERING THEIR ABUNDANCES IN
THE TI ELEMENT, EXCEPT FOR THE TOTAL CROSS SECTONS IN THE
ENERGY RANGE ABOVE 100 KEV.
MT=1 TOTAL
THE DATA AT THE ENERGIES ABOVE 100 KEV WERE EVALUATED BASED ON
THE EXPERIMENTAL ONES/6,7,8/, FOLLOWING FINE STRUCTURES IN
THE MEASURED CROSS SECTIONS. THE DATA IN THE OTHER ENERGY RANGE
WERE CONSTRUCTED FROM THE EVALUATED ONES FOR FIVE ISOTOPES OF
TI.
MT=2 ELASTIC SCATTERING
OBTAINED BY SUBTRACTING THE SUM OF THE PARTIAL CROSS SECTIONS
FROM THE TOTAL CROSS SECTION.
MT=4, 51-87, 91 INELASTIC SCATTERING
THE CROSS SECTIONS WERE TAKEN FROM JENDL FUSION FILE. THE
LEVEL SCHEME WAS BASED ON REF./4/ THE DISCRETE LEVELS WERE
LUMPED AS BELOW:
MT LEVEL ENERGY(MEV) TI-46 TI-47 TI-48 TI-49 TI-50
G.S. 0.0
51 0.1594 51
52 0.8893 51
53 0.9835 51
54 1.2521 52,53
55 1.3818 51
56 1.4442 54
57 1.5421 55 52
58 1.5538 51
59 1.5860 56 53,54
60 1.7235 57,58 55,56
61 2.0098 52
62 2.1630 59,60
63 2.2595 61 57
64 2.2956 62 52
65 2.3440 63,64
66 2.4062 65,66 53 58
67 2.5044 59-62
68 2.6112 53 63 52
69 2.7201 64,65
70 2.9620 54
71 3.0585 55
72 3.1682 56 53
73 3.2133 57,58 55,56
74 3.2990 59
75 3.3332 57-59
76 3.5085 60
77 3.6168 61,62
78 3.6994 63,64
79 3.7386 65
80 3.7710 66 54
81 3.8028 67
82 3.8522 68 55
83 3.9748 56
84 4.1473 57
85 4.1718 58,59
86 4.3110 60
87 4.4105 61
THE THRESHOLD ENERGY FOR THE CONTINUUM OF INELASTIC SCATTERING
WAS SET TO BE 2.416 MEV.
MT=16, 22, 28, 103 (N,2N), (N,NA),(N,NP), (N,P)
ADOPTED FROM JENDL FUSION FILE. THEORETICAL CALCULATION WAS
MADE FOR EACH ISOTOPE WITH SINCROS-II. THE RESULTS WERE
NORMALIZED TO EXPERIMENTAL DATA (SEE COMMENT OF EACH ISOTOPE).
MT=102 CAPTURE
COMPOSED FROM THE ISOTOPIC DATA CALCULATED WITH THE CASTHY
CODE/9/. Q-VALUE IS A MEAN VALUE OF THOSE OF ISOTOPES.
MT=107 (N,A)
COMPOSED FROM THE ISOTOPIC DATA.
MT=251 MU-BAR
CALCULATED BASED ON OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2
CALCULATED WITH THE CASTHY CODE/9/.
MT=51-87
TAKEN FROM JENDL FUSION FILE WHICH WAS CONSTRUCTED FROM THE
ISOTOPIC DATA BY SUMMING UP THE DATA AS SHOWN IN THE TABLE OF
INELASTIC SCATTERING CROSS SECTIONS.
MT=16, 22, 28, 91
TAKEN FROM JENDL FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16, 22, 28, 91
TAKEN FROM JENDL FUSION FILE.
MF=12 PHOTON PRODUCTION MULTIPLICITIES
MT=102 (BELOW 2.5 MEV)
FROM ENERGY BALANCE.
MF=13 PHOTON PRODUCTION CROSS SECTIONS
MT=3 (ABOVE 2.5 MEV)
BASED ON THE CLCULATION WITH THE GNASH CODE/10/, AND THE
MEASUREMENTS BY MORGAN ET AL./11/
MT=4 (BELOW 2.5 MEV)
CALCULATED FROM GAMMA-RAY TRANSITION PROBABILITIES AND CROSS
SECTIONS OF ISOTOPES.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=3, 4, 102
ASSUMED TO BE ISOTROPIC IN THE LABORATORY SYSTEM.
MF=15 CONTINUOUS PHOTON ENERGY SPECTRA
MT=3 (ABOVE 2.5 MEV)
CALCULATED WITH THE GNASH CODE/10/.
MT=102 (BELOW 2.5 MEV)
CALCULATED WITH THE GNASH CODE/10/ EXCEPT FOR THERMAL WHERE
THE SPECTRA WERE CALCULATED WITH CASTHY/9/.
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) HOLDEN, N.E., MARTIN, R.L. AND BARNES, I.L.: PURE & APPL.
CHEM. 56, 675 (1984).
6) FOSTER, JR., D.G. AND GLASGOW D.W.: PHYS. REV. C3,576 (1971).
7) BARNARD, E. ET AL.: CEA-R-4524 (1973).
8) SCHWARZ : NBS-MONO-138 (1974).
9) IGARASI, S. AND FUKAHORI, T.: JAERI 1321 (1991).
10) YOUNG, P.G. AND ARTHUR, E.D.: LA-6947 (1977).
11) MORGAN, G.L.: ORNL/TM-6323 (1978).