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81-Tl- 0 SIU EVAL-DEC93 ZHOU YIMING AND MA GONGGUI
DIST-JAN09 20090105
----JEFF-311 MATERIAL 8100
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
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** Original data taken from: JEFF-3.1 **
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***************************** JEFF-3.1 *************************
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** Original data taken from: JEFF-3.0 **
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***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- CENDL-2.1 (DIST-OCT95)
Set QX to 0. in MF=2
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( INSTITUTE OF NUCLEAR SCIENCE AND TECHNOGY OF
SICHUAN UNIVERSITY, CHENGDU, CHINA )
THE EVALUATION NEUTRON CROSS SECTIONS WERE GIVEN FOR NATURAL
TL IN THE ENERGY RANGE 1.0E-5EV TO 20MEV.(MAT NO.2810) IN
ENDF/B-6 FORMAT
* * * * *
THE THERMAL VALUES CALCULATED BY CODE PSYCHE WERE ADDED BY
LIANG QICHANG IN NOV. 1994:
2200 M/SEC RES. INTEG.(0.5EV CUTOFF)
TOTAL 1.344E+1 B -
ELASTIC 1.001E+1 B -
CAPTURE 3.430E+0 B 1.37248E+1 B
* * * * *
FILE 1
GENERAL DESCRIPTION OF THE EVALUATION AND RELEVANT REFERECES.
A BRIEF SUMMARY OF THE DATA, ALONG WITH THE REFERENCES WAS GIVEN.
DETAILS WILL BE PRESENTED IN THE RELATIVE EVALUATION REPORT.
* * * * *
FILE 2
FILE=2 RESONANCE PARAMETER
RESONANCE REGION FROM 1.0E+2EV TO 50KEV
TAKEN FROM THE RECOMMENDED VALUES OF MUGHABGHAB(1)
* * * * *
FILE 3
MT=1 (TOTAL CROSS SECTION)
BELOW 100 EV, THE DATA OF REF(2-4) WERE USED. ABOVE 50 KEV,
THE DATA OF REF(5-7) WERE USED.
MT=2
THE ELASTIC SCATTERING CROSS SECTION WAS OBTAINED BY SUBTRACTING
THE NON-ELASTIC CROSS SECTION FROM THE EVALUATED TOTAL CROSS
SECTION.
MT=3
THE NON-ELASTIC CROSS SECTION WAS TAKEN FROM THE SUM OF ALL
PARTIAL CROSS SECTIONS.
MT=4 AND MT=51 TO 91
CALCULATED WITH UNF93 CODE(8).
MT=16
THE (N,2N) CROSS SECTION, FROM THRESHOLD TO 15 MEV, WAS
TAKEN FROM THE ISOTOPES DATA OF FREHAUT(9). FROM 15 MEV
TO 20 MEV, THE (N,2N) CROSS SECTION, LEADED BY TL-203'DATA
OF BAYHURST(10).
MT=17 THE (N,3N) CROSS SECTIONS LEADED BY THE DATA OF
BAYHURST(10).
MT=22 AND 28
THE (N,NA) AND (N,NP) CROSS SECTIONS WERE TAKEN FROM UNF93
CODE(8).
MT=102
THE RADIATION CAPTURE CROSS SECTION, BELOW 3MEV, TAKEN FROM THE
DATA (11-13). ABOVE 3 MEV, NORMALIZED CALCULATION DATA(8 ) BY
THE DATA OF BUDNAR(14).
MT=103
(N,P), CROSS SECTIONS USED NORMALIZED MODE CALCULATION (8) BY
QAIM(15)
MT=104, 105
(N,D) AND (N,T) CROSS SECTIONS WERE OBTAINED FROM MODE
CALCULATIONS (8).
MT=107
(N,A) CROSS SECTIONS USED NOMALIZED CALCULATION(8 ) BY
THE DATA OF HANKLA(16) AND POULARIKAS(17).
* * * * *
FILE 4
MT=2,51-66 ELASTIC AND DISCRETE INELASTIC SCATTERING
THE ANGULAR DISTRIBUTIONS WERE CALCULATED VALUE(8 )
MT=16,17,22,28,91
TO BE TAKEN AS ISOTROPIC.
* * * * *
FILE 6
MT=16,17,22,28,91
SECONDARY NEUTRON ENERGY DISTKIBUTION WERE TAKEN FROM
CALCULATION VALUES (8).
* * * * *
OPTICAL MODEL PARAMETERS
DEPTH(MEV) RATIUS(FM) DIFFUSENESS(FM)
V0=53.824 W0=11.02 XR=1.2226 AR=0.763
V1=-0.896 W1=-0.002 XS=1.259 AS=0.356
NEUTRON V2=0.085 W2=-12.0 XV=1.259 AV=0.356
V3=-24.0 U0=-0.36 XS0=1.226 AS0=0.712
V4=0.0 U1=0.113 XC=1.25
VS0=6.2 U2=0.0
V0=54.000 W0=11.800 XR=1.1700 AR=0.750
V1=-0.320 W1=-0.252 XS=1.320 AS=0.510
PROTON V2=0.0 W2= 12.0 XV=1.320 AV=0.510
V3= 24.0 U0=-0.26 XS0=1.100 AS0=0.710
V4=0.4 U1=0.223 XC=1.25
VS0=6.2 U2=0.0
V0=193.00 W0=0.0 XR=1.3700 AR=0.560
V1=-0.150 W1=0.0 XS=1.320 AS=0.510
2-HE-4 V2=0.0 W2= 0.0 XV=1.320 AV=0.510
V3=0.0 U0=21.00 XS0=1.300 AS0=0.560
V4=0.0 U1=0.253 XC=1.30
VS0=6.0 U2=0.0
LEVEL DENSITY PARAMETERS
TL NR NN NP NA NHE3 ND NT N2N NNA N2P N3M
203L7.34 9.64 8.75 14.06 11.14 11.03 13.97 12.6 12.99 8.86 11.53
P0.25 0.72 0.78 0.30 0.72 1.25 0.83 0.30 1.16 0.25 1.16
205L4.18 5.86 5.62 8.86 7.41 7.28 8.75 7.33 11.14 5.76 9.64
P0.0 0.61 0.53 0.25 0.61 1.14 0.78 0.25 0.72 0.0 0.72
L=(0.0088(S(Z)+S(N))+QB)A
P=P(N)+P(Z)
GIANT DIPOLE RESONANCE PARAMETERS(SINGLE PEAK)
TL-203 CSG(B) 2*0.541, 0.481, 2*0.541, 2*0.481, 4*0.541
EE(MEV) 2*13.72, 13.56, 2*13.72, 2*13.56, 4*13.72
GG(MEV) 2*4.61, 3.96, 2*4.61, 2*3.96, 4*4.61
TL-205 CSG(B) 2*0.541, 0.481, 2*0.541, 2*0.481, 4*0.541
EE(MEV) 2*13.72, 13.56, 2*13.72, 2*13.56, 4*13.72
GG(MEV) 2*4.61, 3.96, 2*4.61, 2*3.96, 4*4.61
COUPLED LEVELS(MEV) AND BETA-2
GROUND LEVEL-1 LEVEL-2 BETA-2
TL-203 0.0,0.5(+) 0.2792,1.5(+) 0.6810,2.5(+) 0.12
-205 0.0,0.5(+) 0.2040,1.5(+) 0.6190,2.5(+) 0.12
REFERENCES
(1) S.F.MUGHABGHAB ET AL., NEUTRON RESONANCE PARAMETERS AND
THERMAL CROSS SECTIONS PART B (1984)
(2) KOESTER ET AL., NEANDC(E)-232(5), 51(1982)
(3) K.K.SETH ET AL., P.R.,110, 692(1958)
(4) R.T.CARPENTER ET AL., EXFOR 12189002(1962)
(5) K.K.SETH ET AL., J.PL., 16,306(1965)
(6) M.DIVADEENAM ET AL., DA.B 28 3834(1968)
(7) S.CIERJACKS ET AL., KFK-1000 (1968)
(8) ZHANG JINGSHANG, PROGRAM UNF93, NUCL.SEI.ENG.,114,55(1993)
(9) J.FREHAUT ET AL., EXFOR 20416054, 20416055(1980)
(10) B.P.BAYHURST ET AL., P.R. C 12,451(1975)
(11) V.A.KONKS ET AL., ZET, 47(3),795(1964)
(12) J.H.GIBBONS ET AL., P.R., 122,182(1961)
(13 J.VOIGNIER ET AL., NSE 93,43(1986)
(14) M.BUDNAR ET AL., INDC(YUG)-6,(1979)
(15) S.M.GAIM ET AL., N.P.,A 283,269(1977)
(16) A.K.HANKLA ET AL., N.P., A 180,157(1972)
(17) A.POULARIKAS ET AL., A-ARK-60, 4(1960)
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