7.600000+4 1.885700+2 1 0 2 1
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 272 1
76-Os- 0 FEI EVAL-JAN90 NIKOLAEV M.N.
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 7600
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 + Corrections **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- BROND-2.2 (DIST-OCT91)
19/02/2002: Decay scheme in MF12 modified by A. Hogenbirk
(NRG Petten)
******************************************************************
76-OS- 0
*****************************************************************
CONTENT OF THE FILE:
MF = 1 GENERAL INFORMATION:
MT = 451 COMMENTS ON EVALUATIONS, REFERENCES AND
DICTIONARY.
RESULTS OF EVALUATION FULFILLED BY NIKOLAEV
M.N. (MF = 1-5, 9) AND ZABRODSKAYA S.V.
(MF = 12, 14, 15) ARE GIVEN. DATA COMPILED
AND CHECKED BY SAVOSKINA G.V.
DESCRIPTION IS WRITTEN DOWN BY NIKOLAEV M.N.
0.0253 EV CROSS SECTIONS:
RADIATIVE CAPTURE OS-184 3002.+-150.BARN
RADIATIVE CAPTURE OS-186 79.+-13. BARN
RADIATIVE CAPTURE OS-187 319.+-10. BARN
RADIATIVE CAPTURE OS-188 4.8+-0.5 BARN
RADIATIVE CAPTURE OS-189 25.4+-4. BARN
RADIATIVE CAPTURE OS-190 13.1+-0.3 BARN
RADIATIVE CAPTURE OS-192 1.93+-0.1 BARN
RADIATIVE CAPTURE OS-NAT 15.9+-0.4 BARN
ELASTIC SCATTERING OS-184 108. BARN
ELASTIC SCATTERING OS-186 14.2+-5. BARN
ELASTIC SCATTERING OS-187 10.9+-6. BARN
ELASTIC SCATTERING OS-188 7.6+-0.6 BARN
ELASTIC SCATTERING OS-189 15.3+-1.0 BARN
ELASTIC SCATTERING OS-190 15.9+-0.9 BARN
ELASTIC SCATTERING OS-192 17.9+-0.6 BARN
ELASTIC SCATTERING OS-NAT 15.4+-0.4 BARN
MF = 2 RESONANCE REGION:
MT = 151 ONLY RESOLVED RESONANCE REGION IS DESCRIBED
FOR EVERY OSMIUM ISOTOPE. PARAMETERS ONLY
S-RESONANCE ARE GIVEN. AVERAGE RESONANCE
PARAMETERS NOT GIVEN. LOW ENERGY BOUNDARY OF
RRR IS 10-5 EV FOR EVERY ISOTOPE. PARAMETERS
OF BOUND LEVEL ARE SPECIFIED FOR EVERY
ISOTOPE TO OBTAIN THE EXPERIMENTAL CROSS
SECTIONS VALUE AT 0.0253 EV. PARAMETERS OF
SEVERAL FICTITIOUS RESONANCES ARE GIVEN FOR
ENERGIES GREATER THAN UPPER BOUNDARY OF
RRR FOR TAKING INTO ACCOUNT UNRESOLVED
RESONANCE CONTRIBUTION IN RRR.
---------------------------------------------
! TOTAL ! UPPER ! NUMBER OF
ISOTOPE! NUMBER OF ! BOUNDARY, ! ARTIFICIAL
! RESONANCES ! EV ! RESONANCES
---------------------------------------------
OS-184 1 160 -
OS-186 133 3360 5
OS-187 182 990 5
OS-188 107 5000 5
OS-189 27 77 5
OS-190 7 150 4
OS-192 4 150 1
---------------------------------------------
MF = 3 NEUTRON CROSS-SECTIONS:
IN THE REGION FROM 10-5 EV TO 77 EV ALL CROSS SECTIONS
ARE FULLY DETERMINED BY RESONANCE PARAMETERS LISTED IN
MF=2. IN THE FILE MF=3 ALL CROSS SECTIONS IN THIS
REGION PUT EQUAL TO ZERO. ABOVE THE 77 EV CONTRIBUTION
OF OS-189 IS TAKEN INTO ACCOUNT IN THE FILE MF=3. ABOVE
150 EV CONTRIBUTIONS OF OS-190 AND OS-192 ARE TAKEN
INTO ACCOUNT ALSO. ABOVE 990 EV AND TO 5000 EV
CONTRIBUTION OF OS-187 IS TAKEN INTO ACCOUNT ALSO.
THESE CONTRIBUTIONS WERE CALCULATED WITH THE HELP OF
EVPAR CODE [1] ON THE BASIS OF AVERAGE RESONANCE
PARAMETERS. ABOUT DETERMINATION OF CROSS SECTIONS ABOVE
5000 EV SEE BELOW.
MT = 1 TOTAL CROSS SECTION FROM 5 KEV TO 100 KEV WAS
CALCULATED ON THE BASIS OF AVERAGE
PARAMETERS. ABOVE 100 KEV - FROM THE EYE
GUIDE CURVE FROM [2].
MT = 2 ELASTIC SCATTERING CROSS SECTION ABOVE 5 KEV
IS EQUAL TO DIFFERENCE BETWEEN TOTAL CROSS
SECTION AND SUMMARIZED NONELASTIC CROSS
SECTION.
MT = 4 INELASTIC SCATTERING CROSS SECTION IS THE SUM
OF MT = 51-67 AND MT = 91.
MT = 16 CROSS SECTION OF (N,2N) REACTION WAS
CALCULATED BY TNG CODE [3] FOR EVERY ABUNDANT
ISOTOPE. FOR OS-184, OS-186 AND OS-192
PARAMETERS OF CALCULATION WERE FITTED FOR
AGREEMENT WITH EXPERIMENTAL DATA. FOR OS-187
PARAMETERS OF OS-189 WERE USED. FOR OS-190
PARAMETERS OF OS-192 WERE USED. ABOVE THE
THRESHOLD OF (N,3N) REACTION COMPETITION OF
THIS REACTION WAS TAKEN INTO ACCOUNT.
MT = 17 CROSS SECTION OF (N,3N) REACTION CALCULATED
BY MULTIPLYING OF SUMMARIZED (N,2N) AND
(N,3N) CROSS SECTION CALCULATED BY TNG CODE
ON THE PROBABILITY OF EMISSION OF THIRD
NEUTRON CALCULATED BY NEVA CODE [4]
MT = 51-67 LEVEL EXCITATION CROSS SECTION WERE
CALCULATED BY TNG CODE WITH THE NEXT LEVEL
PARAMETERS
MT ISOTOPE EN,KEV SPIN,PARITY
51 189 31 9/2-
52 189 36 1/2-
53 189 69 5/2-
54 189 95 3/2-
55 188 155 2+
56 190 187 2+
57 192 206 2+
58 189 217 7/2-
59 189 219 7/2-
60 189 234 3/2-
61 189 276 5/2-
62 189 439 5/2-
63 188 478 4+
64 192 489 2+
65 190 548 4+
66 192 580 4+
67 192 690 3+
INELASTIC SCATTERING ON THE LIGHT ISOTOPES
WITH LOW ABUNDANCE WAS TAKEN INTO ACCOUNT BY
CORRESPONDING INCREASING OS-188 ABUNDANCE
WHEN CROSS SECTIONS FOR NATURAL OSMIUM WAS
CALCULATED.
MT = 91 CONTINUUM INELASTIC CROSS SECTION CALCULATED
ON THE BASIS OF STATISTICAL MODEL. BELOW THE
THRESHOLD OF (N,3N) REACTION THIS CROSS
SECTION CALCULATED BY TNG CODE. ABOVE THIS
THRESHOLD CONTINUUM INELASTIC CROSS SECTION
IS THE DIFFERENCE BETWEEN SUM OF CROSS
SECTIONS MT = 4 + 16 + 17 + 102 + 103 + 107
CALCULATED BY TNG CODE AND SUM ADOPTED CROSS
SECTIONS OF (N,2N), (N,3N), (N,GAMMA), (N,P)
AND (N,ALFA).
MT = 102 ISOTOPE CAPTURE CROSS SECTIONS FROM 5 KEV
TO 1 MEV ADOPTED AS IN THE EYE GUIDE CURVES
IN REF.[2] (FOR OS-190 AND OS-192
IRREGULARITIES ON THESE CURVES WERE
SMOOTHED). CROSS SECTION FOR NATURAL OSMIUM
WAS THEN CALCULATED. ABOVE 1 MEV FOR NATURAL
OSMIUM THE PLATINUM RADIATIVE CAPTURE CROSS
SECTION WAS ADOPTED AFTER RENORMALIZATION ON
EVALUATED OSMIUM CROSS SECTION AT 1 MEV. (IN
REF.[2] CROSS SECTION CURVES FOR OS-186,
OS-187, OS-188 ARE SHARPLY INCREASED ON THE
BASIS OF DATA OF REF.[5]. SO ANOMALOUS
BEHAVIOR OF CROSS SECTIONS FOR ALL MEASURED
ISOTOPES LEAD TO DOUBT IN THIS DATA).
MT = 103, 107 (N,P) AND (N,ALFA) CROSS SECTIONS WERE
CALCULATED BY TNG CODE WITH FITTING OF
PARAMETERS OF CALCULATION FOR AGREEMENT WITH
EXPERIMENTAL DATA.
MT = 251, 252, 253 ARE CALCULATED ON THE
BASIS OF MF = 4, MT = 2 DATA.
MF = 4 ANGULAR DISTRIBUTIONS:
MT = 2 ELASTIC SCATTERING ANGULAR DISTRIBUTION
ACCEPTED AS THOSE FOR PLATINUM (ENDF/B-4
DATA).
MT = 16, 17, 51-67, 91 (N,2N), (N,3N) AND INELASTIC
SCATTERING NEUTRON ANGULAR DISTRIBUTIONS
ACCEPTED AS ISOTROPIC IN THE LAB SYSTEM.
MF = 5 ENERGY DISTRIBUTIONS:
MT = 16, 17, 91 CONTINUOUS ENERGY DISTRIBUTIONS
(N,2N), (N,3N) AND INELASTIC SCATTERING
NEUTRONS ARE CALCULATED BY THE NEVA CODE [8]
IN THE FRAME OF EVAPORATION MODEL.
EVAPORATION TEMPERATURES WERE ESTIMATED
ACCORDING TO GILBERT-CAMERON PRESCRIPTION.
COMPETITION FROM THE RADIATIVE CHANNEL WAS
NOT TAKEN INTO ACCOUNT. PRECOMPOUND EMISSION
WAS TAKEN INTO ACCOUNT APPROXIMATELY.
MF = 12 MULTIPLICITIES OF RADIATIVE TRANSITIONS.
MT = 16, 17 MULTIPLICITIES OF CONTINUOUS ENERGY
SPECTRA PHOTONS EMITTED IN (N,2N) AND (N,3N)
REACTIONS IS ADOPTED AS FOR IRIDIUM BECAUSE
RESULTS OF CALCULATIONS OF THESE SPECTRA BY
TNG CODE FOR OSMIUM AND IRIDIUM WERE FINDED
VERY CLOSE ONE TO ANOTHER.
MT = 51-67 FOR EACH OF THIS REACTIONS LINE PHOTON
SPECTRUM ARE GIVEN. PHOTON LINES WERE
DETERMINED OR BY TRANSITIONS ON THE
UNDERLYING LEVELS OR IN THE CASE OF INTERNAL
CONVERSION BY CORRESPONDING ROENTGEN. OPTION
L0=1 IS USED.
MT = 91 PHOTON SPECTRA FOR INELASTIC SCATTERING WITH
CONTINUOUS NEUTRON SPECTRA WERE ALSO ADOPTED
CONTINUOUS. THIS PHOTON SPECTRA WERE WEIGHTED
FOR AVERAGE ISOTOPE SPECTRA. THE LAST WAS
CALCULATED FOR THE MAIN OSMIUM ISOTOPES BY
TNG CODE.
MT = 102 CONTINUOUS RADIATIVE CAPTURE PHOTON SPECTRA
WERE ADOPTED. THESE SPECTRA AND
MULTIPLICITIES WAS TAKEN BY AVERAGING OF
CONTRIBUTIONS OF ODD AND EVEN OSMIUM ISOTOPES
CALCULATED BY TNG CODE.
MT = 103, 107 SPECTRA AND MULTIPLICITIES OF PHOTONS
EMITTED IN (N,P) AND (N,ALFA) REACTIONS WERE
CALCULATED BY TNG CODE.
MF = 14 PHOTON ANGULAR DISTRIBUTIONS:
MT = 16, 17, 51-67, 91, 102, 103, 107 ALL PHOTON
ANGULAR DISTRIBUTIONS WERE TAKEN ISOTROPIC IN
LAB. SYSTEM.
MF = 15 CONTINUOUS PHOTON SPECTRA.
MT = 16, 17, 51-67, 91, 102, 103, 107 SEE COMMENTS
TO MF = 12.
REFERENCES
1. MANTUROV G.N. ET AL. VANT "YADERNYE CONSTANTY" ISSUE
1(50),P.50. MOSCOW, 1983.
2. NEUTRON CROSS SECTIONS. V2. NEUTRON CROSS SECTIONS
CURVES. V.MCLANE, C.L.DUNFORD, P.F.ROSE. NNDC BNL,
ACADEMIC PRESS 1988.
3. SHIBATA K., FU C.Y. ORNL/TM-10093, 1986.
4. NIKOLAEV M.N. AND GILFANOVA O. NEVA - CODE FOR
CALCULATION OF SPECTRA CONSEQUENTLY EVAPORATED
NEUTRONS. FEI, 1988. UNPUBLISHED.
5. WINTERS ET.AL. PHYS.REV.C.21, P.563 (1980).
************************ C O N T E N T S ************************
(MF) (MT) (CARDS)
1 451 277
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