26-Fe- 0
26-FE- 0 JNDC EVAL-MAR87 S.IIJIMA,H.YAMAKOSHI
DIST-SEP89 REV2-MAR94
----JENDL-3.2 MATERIAL 2600
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 EVALUATION WAS PERFORMED FOR JENDL-3.
87-05 COMPILED BY K.SHIBATA (JAERI).
***** JENDL-3.2 ************************************************
92-09 MODIFICATION WAS MADE FOR TOTAL AND ELASTIC SCATTERING
CROSS SECTIONS.
93-11 THE RESONACE PARAMETERS OF FE-58 WERE MODIFIED.
INEALSTIC SCATTERING CROSS SECTIONS WERE REEVALUATED BY
K. SHIBATA (JAERI). DISCRETE LEVELS WERE LUMPED SO THAT
REACTION KINEMATICS COULD BE PROPERLY TAKEN INTO ACCOUNT.
FILES 4 AND 5 FOR MT=16,22,28,91 WERE OBTAINED FROM THE
FILE-6 OF THE JENDL FUSION FILE /16/.
GAMMA PRODUCTION DATA WERE REVALUATED BY S.IGARASI (NEDAC).
94-03 FOR (3,3),(3,107),(13,107), SMALL CROSS-SECTION VALUES
WERE REPLACED WITH 0.0.
******************************************************************
NATURAL IRON DATA CONSTRUCTED FROM FE-ISOTOPES.
MF=1 GENERAL INFORMATION
MT=451 DESCRIPTIVE DATA AND DICTIONARY
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCES
RESONANCE REGION = 1.0E-5 EV TO 250.0 KEV
THE MULTILEVEL BREIT-WIGNER FORMULA WAS USED. PARAMETERS
WERE ADOPTED FROM THE FOLLOWING SOURCES.
FE-54 : PANDEY+/1/ FOR 0 - 680 KEV. R=5.6 FM
FE-56 : PEREY+/2/ FOR -2.0 - 400 KEV. R=5.4 FM FROM FIT-
TING TO TOTAL CROSS SECTION BELOW 60 KEV.
PARAMETERS OF THE 1.15 KEV RESONANCE WERE
TAKEN FROM THE RESULT OF THE NEANDC TASK
FORCE /3/.
FE-57 : ALLEN+/4/ FOR S-WAVE RESONANCES, AND BEER+/5/
FOR P-WAVE RESONANCES IN 0 - 185 KEV.
FE-58 : MUGHABGHAB+/6/.
FOR FE-56, A NEGATIVE LEVEL WAS ADDED AT -3.75 KEV WITH
NEUTRON WIDTH OF 100 EV AND GAMMA WIDTH OF 1.0 EV. NEUTRON
WIDTH OF 27.67-KEV RESONANCE WAS TAKEN AS 1420 EV.
CALCULATED 2200-M/S CROSS SECTIONS AND RES. INTEGRALS.
2200-M/S RES. INTEG.
ELASTIC 11.36 B -
CAPTURE 2.56 B 1.340 B
TOTAL 13.92 B -
MF=3 NEUTRON CROSS SECTIONS
BELOW 250 KEV, BACKGROUND CROSS SECTIONS WERE GIVEN.
MT=1 TOTAL
FOR ENERGIES 250 KEV - 20 MEV, FINE RESOLUTION DATA WERE
TAKEN BY EYE-GUIDE USING INTERACTIVE DISPLAY OF NDES (
NEUTRON DATA EVALUATION SYSTEM) DEVELOPED BY T.NAKAGAWA AT
THE NUCLEAR DATA CENTER, JAERI. THE FOLLOWING DATA WERE
MAINLY ADOPTED:
BELOW 500 KEV : PATTENDEN+/12/
500 KEV - 4.7MEV : CARLSON+/7/
4.7 MEV - 12 MEV : CIERJACKS+/8/
BY CONSIDERING EXPERIMENTAL RESOLUTION, CROSS SECTION SHAPE
WAS MADE SHARPER.
MT=2 ELASTIC SCATTERING
GIVEN AS TOTAL MINUS NONELASTIC CROSS SECTIONS
MT=3 NONELASTIC
SUM OF MT=4,16,22,28,102,103,107
MT=16,22,28,103
CALCULATED USING GNASH /9/.
MT=4,51-90,91 INELASTIC SCATTERING
ISOTOPIC DATA WERE OBTAINED FROM THE CASTHY/10/ AND GNASH
CALCULATIONS. ISOTOPIC LEVELS WERE GROUPED INTO 25
LEVELS OF NATURAL ELEMENT. THE CONTRIBUTIONS FROM THE
DIRECT PROCESS WERE INCLUDED IN THE LEVELS OF MT=55,58,
64,66,68,69,88,90.
OPTICAL POTENTIAL PARAMETERS USED IN THE CALCULATION ARE
AS FOLLOWS:
V = 46.0-0.25*E , R0=1.286, A0=0.620
WS = 14.0-0.2*E , RS=1.390, AS=0.700
14.8-0.2*E FOR FE-57
VSO= 6.0 , RSO=1.07 ,ASO=0.620
ENERGIES IN MEV UNIT, LENGTHS IN FM UNIT.
***** JENDL-3.2 **************************************
FOR MT=51, RESONANCE STRUCTURE OF FE-57 WAS TAKEN INTO
ACCOUNT.
MT=55 (1ST LEVEL OF FE-56)
850 KEV - 2.15 MEV
EVALUATED ON THE BASIS OF THE MEASUREMENTS/12,13/.
2.15 MEV - 4.6 MEV
MODIFIED BY CONSIDERING THE JENDL-2 DATA.
MT=61,66,68,70 (2ND,3RD,4TH AND 5TH LEVELS OF FE-56)
THESE CROSS SECTIONS WERE MODIFIED AROUNF THRESHOLD BY
CONSIDERING THE MEASUREMENTS/14,15/.
MT=68,70,76-79,81-85,88,91
ABOVE 10 MEV, THESE CROSS SECTIONS WERE SLIGHTLY MODIFIED
ACCORDING TO THE JENDL FUSION FILE/16/, WHICH WAS
OBTAINED FROM SINCROS-II /17/ CALCULATIONS.
********************************************************
MT=102 CAPTURE
BACKGROUND CROSS SECTION WAS GIVEN BELOW 250 KEV.
ABOVE 250 KEV, THE CASTHY CALCULATION WAS ADOPTED.
MT=107 (N,ALPHA)
FOR FE-56, THE EVALUATION WAS MADE ON THE BASIS OF
EXPERIMENTAL DATA. FOR FE-54,57,58, THE GNASH CALCULATION
WAS ADOPTED.
MT=251 MU-BAR
CALCULATED WITH CASTHY /10/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-90
OPTICAL AND STATISTICAL-MODEL CALCULATIONS.
THE C.C. CALCULATIONS WERE ADDED TO THE LEVELS OF MT=55,
58,61,63,64,65,70,73,74.
MT=16,22,28,91
OBTAINED FROM JENDL FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,22,28,91
OBTAINED FROM JENDL FUSION FILE.
MF=12 PHOTON MULTIPLICITIES
MT=3
MULTIPLICITIES WERE CALCULATED USING GNASH.
MT=102
CALCULATED WITH CASTHY.
MF=13 PHOTON PRODUCTION CROSS SECTIONS
MT=4,103,107
BELOW 2.5 MEV, DISCRETE GAMMAS WERE GIVEN.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=3,4,102,103,107
ASSUMED TO BE ISOTROPIC.
MF=15 PHOTON ENERGY DISTRIBUTIONS
MT=102
BELOW 10 KEV, CALCULATED WITH CASTHY.
ABOVE 10 KEV, BASED ON THE DATA OF IGASHIRA ET AL./11/.
MT=3,103,107
CALCULATED WITH GNASH.
REFERENCES
1) PANDEY M.S. ET AL.: PROC. CONF. NUCLEAR CROSS SECTIONS AND
TECHNOLOGY, WASHINGTON D.C., (1975), P.748.
2) PEREY F.G. ET AL.: PROC. SPECIALIST MEETING ON NEUTRON DATA
OF STRUCTURAL MATERIALS FOR FAST REACTORS, GEEL, (1977),
P.530.
3) NAKAJIMA Y.: JAERI-M 85-035, P.196 (1985).
4) ALLEN B.J. ET AL.: PROC. SPECIALIST MEETING ON NEUTRON DATA
OF STRUCTURAL MATERIALS FOR FAST REACTORS, GEEL, (1977),
P.476.
5) BEER H. AND SPENCER R.R.: KFK-2063 (1974).
6) MUGHABGHAB S.F. ET AL.: "NEUTRON CROSS SECTIONS, VOL. 1,
PART A", ACADEMIC PRESS (1981).
7) CARLSON A.D. AND CERBONE R.J.: NUCL. SCI. ENG., 42, 28
(1970).
8) CIERJACKS S. ET AL.: KFK-1000 (1968).
9) YOUNG P.G. AND ARTHUR E.D.: LA-6947 (1977).
10) IGARASI S. : J. NUCL. SCI. TECHNOL., 12, 67 (1975).
11) IGASHIRA M. ET AL.: PROC. INT. CONF. NUCLEAR DATA FOR
SCIENCE AND TECHNOLOGY, MITO, 1988, P.67, (1988).
12) VOSS F. ET AL.: PROC. INT. CONF. ON NEUTRON CROSS SECTIONS
AND TECHNOLOGY, KNOXVILLE 1971, P.191 (1971).
13) SMITH D.L.: ANL/NDM-20 (1976).
14) HOPKINS J.C. AND SILBERT M.G.: NUCL. SCI. ENG.,19,431(1964).
15) GILBOY W.B. AND TOWLE J.H.: NUCL. PHYS., 64, 130 (1965).
16) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).
17) YAMAMURO N.: JAERI-M 90-006 (1990).