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63-Eu-151 NEA RCOM-JUN82 H.GRUPPELAAR,H.CH.RIEFFE
JNDF-22 DIST-JAN09 20090105
----JEFF-311 MATERIAL 6325
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
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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 :- JEF-2.2 (DIST-JAN92)
Minor Correction in first line of MF/MT:13/3, L1=0 not 1
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* JEF-2 *
* DATA WERE TAKEN FROM ENDF/B-V(MAT=1357). *
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* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
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COMPILATION
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1) THE Q-VALUES AND THRESHOLD ENERGIES ORIGINALLY GIVEN FOR
(N,2N) AND (N,NP) REACTIONS ARE NOT CONSISTENT. THEIR THRESHOLD
ENERGIES WERE MODIFIED AS FOLLOWS;
(N,2N) FROM 8.02342 MEV TO 8.02377 MEV,
(N,NP) FROM 4.92247 MEV TO 4.92268 MEV.
2) THE TOTAL AND TOTAL INELASTIC SCATTERING CROSS SECTIONS WERE
RE-CALCULATED FROM PARTIAL CROSS SECTIONS.
BNL EVAL-DEC77 S.F. MUGHABGHAB
DIST-APR79 781102
THIS MATERIAL CONTAINS NEUTRON AND GAMMA-RAY PRODUCTION CROSS
SECTIONS FOR EUROPIUM ISOTOPES EU-151. IN THE ENDF/B-II FILES,(1)
THE EMPHASIS WAS LAID ON THE EVALUATION OF THE LOW ENERGY NEUTRON
CROSS SECTIONS, AND NOT ON THE EVALUATION OF THE INTERMEDIATE AND
HIGH ENERGY NEUTRON CROSS SECTION DATA. SINCE THE CROSS SECTIONS
OF THE INTERMEDIATE AND HIGH ENERGY RANGES ARE IMPORTANT FOR THE
FAST REACTOR PROGRAM, EXTENSIVE STUDIES WERE CARRIED OUT FOR THE
CROSS SECTIONS, ESPECIALLY THE RADIATIVE CAPTURE CROSS SECTIONS,
IN HIGH ENERGY RANGE.
FILE 2 RESONANCE PARAMETERS
--------------------------------
RESOLVED RESONANCE REGION
THE RESOLVED RESONANCE PARAMETERS RECOMMENDED IN BNL-325,VOL1(2)
THIRD EDITION ARE ADOPTED. WHERE SPIN VALUES ARE NOT DETERMINED,
ASSIGNMENTS ARE MADE RANDOMLY IN ORDER TO SATISFY THE (2J+1)
LEVEL SPACING LAW AND THE J-INDEPENDENCE OF STRENGTH FUNCTION.
THE RESOLVED POSITIVE ENERGY RESONANCES CONTRIBUTE 1430.5B TO
THE THERMAL CAPTURE CROSS SECTION. PARAMETERS OF A BOUND LEVEL
ARE DERIVED TO FIT A MEASURED CAPTURE CROSS-SECTION OF 9200-+100
B (REF 2)
UNRESOLVED RESONANCE PARAMETERS
THE UNRESOLVED RESONANCE REGION,98.81EV-10KEV IS DESCRIBED BY
AVERAGE RESONANCE PARAMETERS OBTAINED FROM REF.2. THE AVERAGE
RADIATIVE WIDTH FOR S-WAVE RESONANCES WAS INCREASED FROM 91.17
MV TO 98MV IN ORDER TO FIT MEASUREMENTS IN THE ENERGY REGION OF
100 EV TO 10 KEV.
4. FILE 3 (NEUTRON CROSS SECTIONS)
4.1 TOTAL CROSS SECTION (MT = 1)
SEVERAL MEASUREMENTS OF THE TOTAL CROSS SECTION IN THE LOW ENERGY
RANGE WERE EVALUATED AND REPRESENTED AS RESOLVED RESONANCE
PARAMETERS. IN THE INTERMEDIATE ENERGY RANGE BETWEEN 0.8 KEV - 24
KEV, THE TOTAL CROSS SECTION OF NATURAL EUROPIUM WAS MEASURED BY
EGELSTAFF.(3) COMPARED TO THE RECENT MEASUREMENTS BY RAHN (4) FOR
EU-151 ENERGY RANGE OF 0.2 KEV TO 3 KEV). EGELSTAFF'S DATA IS
ABOUT 30% TOO SMALL. THE SMOOTH TOTAL CROSS SECTION CALCULATED
USING THE UNRESOLVED RESONANCE PARAMETER AGREES WITH RAHN'S DATA
WITHIN 10%. ALTHOUGH RAHN'S TOTAL CROSS SECTION DATA SHOW THE
RESONANCE SHAPE AND THE AVERAGE VALUES OVER SEVERAL RESONANCES
FLUCTUATE, THE DATA WERE REPRESENTED AS UNRESOLVED RESONANCE
PARAMETERS, SO THAT SELF SHIELDING AND THE DOPPLER EFFECT COULD BE
CALCULATED. BECAUSE OF NO DATA BETWEEN 30 KEV TO 2.3 MEV, THE
TOTAL CROSS SECTION WAS CALCULATED BY THE OPTICAL MODEL USING
MOSTLY BESCHETTI AND GREENLEES' OPTICAL PARAMETERS. (5)
BETWEEN 2.3 MEV TO 15 MEV, THE DATA OBTAINED BY FOSTER ET AL. (6)
FOR NATURAL EUROPIUM WERE TAKEN. ABOVE THIS ENERGY RANGE, THE
TOTAL CROSS SECTION WAS EVALUATED FROM A COMPARISON BETWEEN THE
OPTICAL MODEL CALCULATION AND FOSTER'S DATA.
4.2 ELASTIC SCATTERING CROSS SECTION (MT = 2)
THE ELASTIC SCATTERING CROSS SECTIONS IN THE ENERGY HIGHER THAN
THE UNRESOLVED RESONANCE ENERGY WERE OBTAINED BY SUBSTRUCTING THE
NON-ELASTIC CROSS SECTION FROM THE EVALUATED TOTAL CROSS SECTION.
4.3 NONELASTIC SCATTERING CROSS SECTION (MT = 3)
THE NONELASTIC SCATTERING CROSS SECTION WAS CALCULATED BY SUMMING
UP ALL CROSS SECTIONS EXCEPT THE ELASTIC SCATTERING CROSS SECTION.
4.4 INELASTIC SCATTERING CROSS SECTION (MT = 4, 51, 52 .... 91)
THE INELASTIC SCATTERING CROSS SECTIONS WERE GIVEN AS TOTAL (MT =
4), DISCRETE LEVEL EXCITATION CROSS SECTION (MT = 51 ...) OF THE
FIRST 9 LEVELS AND CONTINUUM LEVEL EXCITATION CROSS SECTION (MT =
91). THE LEVEL SCHEME FOR THESE DISCRETE LEVELS IS TAKEN FROM (7),
(8),(9),(10),(11),(12),(13).
THE INDIVIDUAL LEVEL EXCITATION CROSS SECTIONS, WERE CALCULATED
USING THE CODE COMNUC-3 (14,15) FOR THE NEUTRON ENERGIES UP TO 3
MEV. THE INELASTIC SCATTERING CROSS SECTION FOR DISCRETE LEVEL
EXCITATION ABOVE 3 MEV WAS NEGLECTED AND THE INELASTIC SCATTERING
CROSS SECTION FOR CONTINUUM LEVEL EXCITATION WAS CALCULATED
BY THE CASCADE CALCULATION OF GROGI-3. (16,17) THE LEVEL DENSITY
PARAMETERS FOR THE CONTINUUM OF LEVELS WERE TAKEN FROM THE COOK
DATA (18) FOR DEFORMED NUCLEI USING THE GILBERT-CAMERON FORMULA.
(19)
4.5 (N,P) AND (N,N',P) CROSS SECTIONS (MT '=103, 28)
THE STATISTICAL MODEL CALCULATION BASED ON THE COMPOUND NUCLEAR
PROCESS FOR THE (N,P) CROSS SECTION PRODUCES A VERY SMALL CROSS
SECTION COMPARED TO THE EXPERIMENTAL VALUES OBTAINED BY KENNA (20)
AT 14.0 MEV. AND THERE ARE NO OTHER EXPERIMENTAL DATA FOR OTHER
NEUTRON ENERGIES. THE CROSS SECTION CURVE OF (N,P) REACTIONS
CALCULATED BY THE SEMI-EMPIRICAL STATISTICAL MODEL CODE THRESH
(21,22) WAS ADAPTED AFTER IT WAS NORMALIZED TO THE EXPERIMENTAL
VALUES MENTIONED ABOVE.
NO CROSS SECTION MEASUREMENT FOR (N,N'P) REACTION IS AVAILABLE,
SO THAT THIS CROSS SECTION WAS CALCULATED BY USING THE GROGI-3
CODE.
4.6 (N,ALPHA) AND (N,N'ALPHA) CROSS SECTIONS (MT = 107, 22)
THESE CROSS SECTIONS WERE CALCULATED IN THE SAME WAY AS THE (N,P)
AND (N,N'P) CROSS SECTIONS. THE CROSS SECTIONS FOR THE (N,ALPHA)
REACTION CALCULATED USING GROGI-3 CODE ARE VERY SMALL COMPARED
WITH THE EXPERIMENTAL VALUES BY RAMA PRASAD ET AL. (23) SO THAT
THE CROSS SECTION CURVES WERE CALCULATED BY THE THRESH CODE, AND
THE VALUES NORMALIZED TO THE ABOVE EXPERIMENTAL VALUES.
FURTHERMORE, THE (N,ALPHA) CROSS SECTION AT THERMAL NEUTRON ENERGY
(24) WHICH IS NOT NEGLIGIBLY SMALL (9.0+/- 2.0 MB), WAS ADDED OVER
THE WHOLE ENERGY RANGE .00001 EV TO 20 MEV AS A BACKGROUND.
NO EXPERIMENTAL DATA ARE AVAILABLE FOR (N,N'ALPHA) REACTION CROSS
SECTION, AND THE CROSS SECTION WAS CALCULATED USING GROGI-3 CODE.
4.7 (N,2N), (N,3N) CROSS SECTIONS (MT=16)(MT=17)
THE SEVERAL (N,2N) CROSS SECTIONS IN WHICH THE RESIDUAL NUCLEUS
GOES TO THE META STABLE STATE WITH 12.6 H FOR HALF LIFE HAVE BEEN
MEASURED AT 14.8 MEV. (25,26,27) THESE DATA AGREE WITHIN 20% WITH
EACH OTHER. HOWEVER, THESE VALUES (ABOUT 0.5 BARN) ARE SMALL
COMPARED TO THE VALUE (ABOUT 2 BARN) CALCULATED USING THE
STATISTICAL MODEL. NEIGHBOURING NUCLEI SHOW THAT THE (N,2N) CROSS
SECTION, IN WHICH THE RESIDUAL NUCLEUS GOES TO THE OTHER
METASTABLE STATE AND THE GROUND STATE ARE OF SIMILAR MAGNITUDE SO
THAT THE VALUES CALCULATED BY GROGI-3 CODE WERE ADOPTED AS THE
EVALUATED DATA.
FOR (N,3N) REACTION, NO EXPERIMENTAL RESULTS ARE AVAILABLE, SO
THAT THE VALUES CALCULATED BY GROGI-3 WERE ADOPTED.
4.8 (N,D),(N,T)AND(N,HE-3) REACTION CROSS SECTION(MT=104,105,107)
NO EXPERIMENTAL DATA ARE AVAILABLE, SO THAT THE VALUES
CALCULATED BY THRESH WERE ADOPTED AS THE EVALUATED DATA.
THE RADIATIVE CAPTURE CROSS SECTION (MT=102)
--------------------------------------------
THE CAPTURE CROSS SECTION IN THE LOW ENERGY REGION,10-5 TO 98 EV
IS REPRESENTED BY THE RESONANCE PARAMETERS.A BOUND LEVEL IS
POSTULATED TO ACCOUNT FOR A CAPTURE CROSS SECTION OF 9200-+100
B. FROM 98.8 EV TO 10 KEV, IT IS REPRESENTED BY AVERAGE
RESONANCE PARAMETERS.
IN THE ENERGY REGION FROM 10KEV TO 360 KEV, THE EVALUATION IS
BASED ON THE EXPERIMENTAL DATA OF KONKS ET.AL.(REF.28) MOXON
ET.AL.(REF.29), HOCKENBURY ET.AL.(REF.30) YURLOV ET.AL.
(REF.31) AND CZIRR(REF.32)
JOHNSRUD ET.AL.(REF.33) MEASURED THE ACTIVATION CROSS SECTION OF
EU-152 9.3 HR METASTABLE STATE BETWEEN 160 KEV AND 2.5 MEV. THIS
CROSS SECTION WAS NORMALIZED BY A FACTOR OF ABOUT 2.3 IN ORDER
TO OVERLAP WITH YURLOV ET.AL. MEASUREMENT AND TO REPRESENT THE
TOTAL CAPTURE CROSS SECTION OF EU151.THIS PROCEDURE SEEMS TO BE
JUSTIFIED IN VIEW OF THE INTEGRAL RESULTS OF ANDERL ET.AL.
(REF.34)
ABOVE 2.5 MEV,WHERE EXPERIMENTAL MEASUREMENTS ARE NOT AVAILABLE,
THE CAPTURE CROSS SECTION IS BASED ON COMNUC CALCULATIONS
(REF.35) NORMALIZED TO A VALUE OF 1 MB AT 14.7 MEV.
AFTER THE COMPLETION OF THE EVALUATION, THE CAPTURE CROSS
SECTION WAS AVERAGED OVER A 620-POINT CFRMF SPECTRUM. THE VALUE
OBTAINED IS 2.38 B. THIS COMPARES FAVORABLY WITH A MEASURED
VALUE OF 2.61-+0.16B.(REF.36)
5. FILE 4 (ANGULAR DISTRIBUTION OF SECONDARY NEUTRONS)
5.1 ELASTIC SCATTERING (MT = 2)
NO EXPERIMENTAL DATA WERE AVAILABLE, SO THE VALUES CALCULATED BY
ABACUS-2(37) USING THE OPTICAL MODEL WAS ADOPTED AS THE
EVALUATED DATA. THE LEGENDRE COEFFICIENTS, CALCULATED BY CHAD
(38) WERE GIVEN IN FILE 4
5.2 INELASTICALLY SCATTERED NEUTRONS (N,2N),(N,3N),(N,N'P),
AND(N,N'ALPHA) REACTION (MT=51...,91,MT=16,17,22,23)
NEUTRONS FROM THESE REACTIONS WERE ASSUMED TO BE ISOTOPIC IN THE
CENTER OF MASS SYSTEM.
6. FILE 5 (ENERGY DISTRIBUTION OF SECONDARY NEUTRONS)
6.1 (N,2N),(N,3N) AND (N,N') REACTIONS (MT=16,17, AND 91)
THE EFFECTIVE TEMPERATURE OF THESE MAXWELLIANS WERE OBTAINED BY
THE WEISKOPF FORMULA.(39)
7. FILE 12 MULTIPLICITIES AND TRANSITION PROBABILITY ARRAY
7.1 RADIATIVE CAPTURE GAMMA-RAY MULTIPLICITY
GROSHEV'S AND SHERA'S DATA(40,41)WERE USED AS EVALUATED DATA
FOR THE RADIATIVE CAPTURE REACTION(MT=102) BETWEEN 0.00001 EV TO
1 MEV NEUTRON ENERGY
THERE IS NO EXPERIMENTAL DATA FOR NEUTRON ENERGIES LARGER THAN
1 MEV. SO THE GAMMA RAY PRODUCTION CROSS SECTIONS FOR ALL
REACTIONS WERE CALCULATED BY THE GROGI-3 CODE.
7.2 TRANSITION PROBABILITY ARRAY FOR GAMMA RAY DUE TO INELASTIC
NEUTRON SCATTERING
THE EVALUATED TRANSITION PROBABILITIES WERE CALCULATED FROM REF
(7,9,11,42).MOST DATA WERE TAKEN FROM (11)
8. FILE 14 (ANGULAR DISTRIBUTION OF GAMMA RAYS)
ALL GAMMA RAY PRODUCED BY NEUTRON CAPTURE, INELASTIC AND NON
ELASTIC SCATTERING ARE ASSUMED TO BE ISOTOPIC.
9. FILE 15 (ENERGY DISTRIBUTION OF SECONDARY GAMMA RAYS)
FOR THERMAL NEUTRON CAPTURE THEY ARE EXPRESSED BY HYSTOGRAM TYPE
SPECTRUM WITH 0.25 MEV BIN ENERGY WIDTH. FOR ABOVE 1 MEV NEUTRON
ENERGY, THEY ARE TABULATED WITH 0.5 MEV BIN.
REFERENCES
----------
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BROOKHAVEN NATIONAL LABORATORY REPORT BNL-17541(ENDF-201),1973
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REPORT-BNL-325,VOL1, 3RD. ED. 1973
(3) P.A.EGELSTAFF, SCSRS DATA NO. 60952 (1955).
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