28-Ni- 58
28-NI- 58 NAIG EVAL-MAR87 S.IIJIMA
DIST-SEP89 REV2-SEP93
----JENDL-3.2 MATERIAL 2825
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
87-03 EVALUATION WAS PERFORMED FOR JENDL-3. SHORT DESCRIPTION
ON THE EVALUATION IS GIVEN IN REF./1/
87-05 COMPILED BY K.SHIBATA (JAERI).
90-10 MF=5, MT=16, 22 AND 28: DATA AT THRESHOLD ENERGIES WERE
MODIFIED. MF=12, MT=16, 91 AND 102 WERE SLIGHTLY MODIFIED.
93-09 JENDL-3.2.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(4,16-28), (4,91) TAKEN FROM JENDL FUSION FILE
(5,16-91) TAKEN FROM JENDL FUSION FILE
(12,102) BELOW 500 KEV, REVISED BY S.IGASASI
(15,102) BELOW 500 KEV, REVISED BY S.IGARASI
***********************************************************
-------------------------------------------------------------
JENDL FUSION FILE /2/ (AS OF SEP. 1993)
EVALUATED BY S.CHIBA (NDC/JAERI)
COMPILED BY S.CHIBA
ALL OF CROSS SECTIONS WERE TAKEN FROM JENDL-3. EDX'S OF
MT=16, 22, 28 AND 91 WERE REPLACED BY THOSE CALCULATED
WITH SINCROS-II CODE SYSTEM/3/ IN ORDER TO MAKE THE
AGREEMENT WITH THE EDX OF NATURAL NI MEASURED BY BABA ET
AL./4/ AT 14.1 MEV. DDX'S OF CONTINUUM REACTIONS WERE
CREATED WITH F15TOB PROGRAM /2/. KUMABE'S SYSTEMATICS
/5/ WAS USED. THE PRECOMPOUND/COMPOUND RATIO WAS
CALCULATED BY THE SINCROS-II CODE SYSTEM.
OPTICAL-MODEL, LEVEL DENSITY AND OTHER PARAMETERS USED
IN THE SINCROS-II CALCULATION ARE DESCRIBED IN REF./3/.
LEVEL SCHEMES WERE DETERMINED ON THE BASIS OF ENSDF/6/.
-------------------------------------------------------------
MF=1,MT=451 COMMENTS AND DICTIONARY
MF=2,MT=151 RESOLVED RESONANCE PARAMETERS : 1.0E-5 EV - 420 KEV
EVALUATION BASED ON THE FOLLOWING DATA.
S-WAVE RESONANCE PARAMETERS FROM SYME+/7/
P-WAVE RESONANCE PARAMETERS FROM JENDL-2 AND SYME+/7/
TWO NEGATIVE RESONANCES DUE TO PEREY+/8/ WERE ADOPTED
WITH MODIFICATION:
E = -50 KEV GAMMA-N = 28.0 KEV GAMMA-G = 0.0
E = -6.5 KEV GAMMA-N = 1400 EV GAMMA-G = 2.31 EV
GAMMA WIDTH OF 2.0 EV AND 1.0 EV WERE ASSUMED FOR UNKNOWN
GAMMA WIDTHS OF S-WAVE AND P-WAVE RESONANCES, RESPEC-
TIVELY.
SCATTERING RADIUS : 6.0 FM
CALCULATED 2200 M/S VALUES AND RESONANCE INTEGRALS (BARN):
2200 M/S VALUE RES. INT.
TOTAL 30.754 -
ELASTIC 26.251 -
CAPTURE 4.503 2.16
MF=3 NEUTRON CROSS SECTIONS
BACKGROUND CROSS SECTIONS APPLIED TO THE RESONANCE REGION FOR
MT=1 AND 102. CROSS SECTIONS ABOVE 420 KEV EVALUATED AS
FOLLOWS:
MT=1 : TOTAL CROSS SECTION
BETWEEN 420 KEV TO 677 KEV, EXPERIMENTAL DATA OF FARREL ET
AL./9/ WERE ADOPTED. FROM 677 KEV TO 20 MEV, CALCULATED
WITH OPTICAL MODEL. POTENTIAL PARAMETERS WERE OBTAINED BY
FITTING NAT-NI DATA /10/:
V =51.33 - 0.331*EN ,WS=8.068 + 0.112*EN ,VSO=7.0 (MEV)
R0=RSO=1.24 ,RS=1.40 (FM)
A0=ASO=0.541 ,AS=0.4 (FM)
SURFACE IMAGINARY PART IS IN DERIVATIVE WOODS-SAXON FORM.
MT=2 : ELASTIC SCATTERING
(TOTAL) - (NONELASTIC CROSS SECTIONS).
MT=3 : NONELASTIC CROSS SECTION
SUM OF MT=4,16,22,28,102,103,104,105,106,107,111.
MT=16 (N,2N)
MAINLY BASED ON EXPERIMENTAL DATA OF IKEDA ET AL./11/ AND
PAVLIK ET AL./12/
MT=28 (N,N'P)
OBTAINED BY SUBTRACTIONG THE (N,D) CROSS SECTION CALCULA-
TED WITH PEGASUS FROM THE (N,NP+PN+D)CO-57 CROSS SECTION
BASED ON IKEDA ET AL./11/ AND PAVLIK ET AL./12/ INVERSE
CROSS SECTIONS WERE CALCULATED FROM THE FOLLOWING OMP'S:
PROTON = PEREY/13/
ALPHA = HUIZENGA AND IGO/14/
DEUTERON = LOHR AND HAEBERLI/15/
HELIUM-3 AND TRITON = BECCHETTI AND GREENLEES/16/
MT=22 (N,N'A)
CALCULATED USING THE PEGASUS CODE /17/ AND NORMALIZED TO
EXPERIMENTAL DATA/18/
MT=4,51-65,91 INELASTIC SCATTERING
THE CASTHY /19/ AND GNASH /20/ CALCULATION WAS ADOPTED IN
THE NEUTRON ENERGY REGION BELOW AND ABOVE 7 MEV, RESPEC-
TIVELY. THE DIRECT PROCESS WAS TAKEN INTO ACCOUNT FOR MT=
51, 52, 53, 55 AND 65. FOR THE LEVEL OF MT=65, ONLY THE
DIRECT PROCESS WAS CONSIDERED. THE LEVEL SCHEME USED IS
GIVEN AS FOLLOWS:
NO ENERGY(MEV) SPIN-PARITY
G.S 0.0 0 +
1. 1.4545 2 +
2. 2.4591 4 +
3. 2.7755 2 +
4. 2.9018 1 +
5. 2.9424 0 +
6. 3.0376 2 +
7. 3.2634 2 +
8. 3.4203 3 +
9. 3.5240 4 +
10. 3.5309 0 +
11. 3.5934 1 +
12. 3.6200 4 +
13. 3.7744 3 +
14. 3.8983 2 +
15. 4.4753 3 -
CONTINUUM LEVELS ASSUMED ABOVE 3.932 MEV.
MT=102 CAPTURE
CALCULATED WITH CASTHY. THE GAMMA-RAY STRENGTH FUNCTION
OF 4.616E-5 WAS USED. LEVEL DENSITY PARAMETERS ARE:
PAIRING SPIN-CUTOFF F.
A(1/MEV) T(MEV) ENERGY(MEV) (MEV**0.5) EX(MEV)
-------------------------------------------------------------
NI-58 6.850 1.30 2.47 5.726 9.610
NI-59 7.126 1.325 1.20 5.907 9.250
-------------------------------------------------------------
MT=103 (N,P)
JENDL-2 WAS MODIFIED BY CONSIDERING EXPERIMENTAL DATA;
BELOW 2 MEV, DATA OF SMITH ET AL./21/, AND ABOVE 13 MEV 2
MEV), DATA OF IKEDA ET AL./11/ AND PAVLIK ET AL./12/
PEGASUS CALCULATION WAS ALSO CONSIDERED ABOVE 15 MEV.
MT=104,105,106,107,111 (N,D),(N,T),(N,HE-3),(N,A),(N,2P)
THE CROSS SECTIONS WERE CALCULATED USING THE PEGASUS
CODE /17/. THE (N,T) AND (N,A) CROSS SECTION WAS
NORMALIZED TO THE DATA OF QAIM AND STOECKLIN/22/ AND
GRIMES ET AL./18/, RESPECTIVELY.
MT=251 : MU-BAR
CALCULATED WITH OPTICAL MODEL.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 : CALCULATED WITH OPTICAL MODEL.
MT=51-64 : CALCULATED WITH CASTHY. DIRECT PROCESS
INCLUDED IN MT=51, 52, 53, 55.
MT=65 : C.C. CALCULATION.
MT=16,22,28,91 : APPROXIMATELY TRANSFORMED FROM THE MF=6 DATA
(DDX) OF JENDL FUSION FILE.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,22,28,91 : APPROXIMATELY TRANSFORMED FROM THE MF=6 DATA
(DDX) OF JENDL FUSION FILE.
MF=12 PHOTON MULTIPLICITIES AND TRANSITION PROBABILITY ARRAYS
MT=16,22,28,91,103,107:
MULTIPLICITIES CALCULATED WITH GNASH.
MT=51-65 : TRANSITION PROBABILITY ARRAYS.
MT=102 : MULTIPLICITIES CALCULATED FROM ENERGY BALANCE.
MF=14 PHOTON ANGULAR DISTRIBUTIONS
MT=16,22,28,51-65,91,102,103,107:
ISOTROPIC DISTRIBUTIONS.
MF=15 PHOTON ENERGY DISTRIBUTIONS
MT=16,22,28,91,102,103,107:
CALCULATED WITH GNASH. FOR MT=102, SPECTRA WERE
CALCULATED WITH CASTHY, TAKING PRIMARY TRANSITIONS
AT 1.0E-5, 2.53E-2, 1.0E+3 AND 1.0E+4 EV.
REFERENCES
1) IIJIMA S. ET AL.: PROC. INT. CONF. NUCLEAR DATA FOR SCIENCE
AND TECHNOL., MITO, 1988, P.627 (1988).
2) CHIBA S. ET AL.: JAERI-M 92-027, P.35 (1992).
3) YAMAMURO N.: JAERI-M 90-006 (1990).
4) BABA M. ET AL.: PROC. INT. CONF. NUCLEAR DATA FOR SCIENCE
AND TECHNOL., MITO, 1988, P.291 (1988).
5) KUMABE I. ET AL.: NUCL. SCI. ENG., 104, 280 (1990).
6) ENSDF: EVALUATED NUCLEAR STRUCTURE DATA FILE, BNL/NNDL.
7) SYME D.B. ET AL.: NEUTRON DATA OF STRUCTURAL MATERIALS FOR
FBR, 1977 GEEL MEET., P.703, PERGAMON PRESS(1979).
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AND APPLIED SCIENCE, SANTA FE, 1985, P.1639 (1986).
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