Back
90-Th-229 TIT,NEA EVAL-AUG88 N.TAKAGI
DIST-JAN09 20090105
----JEFF-311 MATERIAL 9031
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
** **
** Original data taken from: JEFF-3.1 **
** **
******************************************************************
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
05-01 NEA/OECD (Rugama) 8 delayed neutron groups
Jefdoc-976 (Wilson and England, Prog Nucl Eng 41,71(2002)
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JENDL-3.2 (DIST-SEP90 REV-SEP93)
A. Nouri (Data Bank)
use the same representation as for MT=452
(ENDF-6 recommendation): convert LNU=1
(polynomial (linear) representation) used in
JENDL-32 to tabular representation (LNU=2).
******************************************************************
HISTORY
87-08 NEW EVALUATION WAS MADE BY N. TAKAGI (TOKYO INSTITUTE OF
TECHNOLOGY, TIT) /1/.
94-06 JENDL-3.2.
NU-P, NU-D AND NU-TOTAL WERE MODIFIED.
COMPILED BY T.NAKAGAWA (NDC/JAERI)
***** MODIFIED PARTS FOR JENDL-3.2 ********************
(1,452), (1,455), (1,456)
***********************************************************
MF=1 GENERAL INFORMATION
MT=451 COMMENT AND DICTIONARY
MT=452 NUMBER OF NEUTRONS PER FISSION
SUM OF NU-P NAD NU-D.
MT=455 DELAYED NEUTRONS PER FISSION
AVERAGE VALUES OF SYSTEMATICS BY TUTTLE/2/, BENEDETTI ET
AL./3/ AND WALDO ET AL./4/ DECAY CONSTANTS WERE ADOPTED
FROM THE EVALUATION BY BRADY AND ENGLAND/5/.
MT=456 PROMPT NEUTRONS PER FISSION
BASED ON SYSTEMATICS BY MANERO AND KONSHIN/6/, AND BY
HOWERTON/7/.
MF=2 RESONANCE PARAMETERS
MT=151 RESOLVED RESONANCE PARAMETERS : 1.0E-5 EV TO 9.5 EV
SINGLE-LEVEL BREIT WIGNER FORMULA WAS ADOPTED. PARAMETERS
WERE DETERMINED ON THE BASIS OF RECOMMENDATION OF MUGHABGHAB
/8/. FOR THE LEVELS WHOSE RADIATIVE WIDTH AND/OR FISSION
WIDTH WERE UNKNOWN, AVERAGE GAMMA-G OF 0.043 EV WAS ASSUMED,
FISSION WIDTHS WERE CALCULATED FROM (PEAK SIG)*(GAMMA-F).
EFFECTIVE SCATTERING RADIUS WAS ASSUMED TO BE 10 FM.
2200-M/S CROSS SECTIONS AND RESONANCE INTEGRALS
2200 M/S VALUE RES. INT.
TOTAL 104.09 B -
ELASTIC 9.928 B -
FISSION 30.81 B 444 B
CAPTURE 63.34 B 1236 B
MF=3 NEUTRON CROSS SECTIONS
MT=1 TOTAL CROSS SECTION
ABOVE 9.5 EV, OPTICAL MODEL CALCULATION WAS MADE WITH
CASTHY/9/. THE POTENTIAL PARAMETERS/10/ USED ARE AS
FOLLOWS,
V = 41.0 - 0.05*EN (MEV)
WS= 6.4 - 0.15*SQRT(EN) (MEV)
WV= 0 , VSO = 7.0 (MEV)
R = RSO = 1.31 , RS = 1.38 (FM)
A = ASO = 0.47 , B = 0.47 (FM)
MT=2 ELASTIC SCATTERING CROSS SECTION
OPTICAL MODEL CALCULATION WAS ADOPTED.
MT=4,51-54,91 INELASTIC SCATTERING CROSS SECTIONS.
OPTICAL AND STATISTICAL MODE LCALCULATION WAS MADE WITH
CASTHY/9/. THE LEVEL SCHEME WAS TAKEN FROM REF./11/.
NO ENERGY(KEV) SPIN-PARITY
G.S. 0.0 5/2 +
1 0.1 3/2 +
2 20.0 3/2 +
3 29.2 5/2 +
4 42.5 7/2 +
LEVELS ABOVE 67 KEV WERE ASSUMED TO BE OVERLAPPING.
THE LEVEL DENSITY PARAMETERS WERE TAKEN FROM REF./12/.
MT=16,17,37 (N,2N), (N,3N) AND (N,4N) REACTION CROSS SECTIONS
CALCULATED WITH EVAPORATION MODEL.
MT=18 FISSION CROSS SECTION
ABOVE 9.5 EV, THE CROSS-SECTION SHAPE WAS ASSUMED TO BE
THE SAME AS TH-233 FISSION CROSS SECTION AND IT WAS
NORMALIZED BY THE FACTOR OBTAINED FROM SYSTEMATICS OF
BEHRENS AND HOWERTON/13/.
MT=102 CAPTURE CROSS SECTION
CALCULATED WITH CASTHY. THE GAMMA-RAY STRENGTH FUNCTION
WAS ESTIMATED FROM GAMMA-G = 0.040 EV AND LEVEL SPACING =
0.53 EV.
MT=251 MU-L
CALCULATED WITH CASTHY.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2,51-54,91 CALCULATED WITH OPTICAL MODEL.
MT=16,17,18,37 ISOTROPIC IN THE LAB SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,37 EVAPORATION SPECTRA WERE GIVEN
MT=18 MAXWELLIAN FISSION SPECTRUM. TEMPERATURE
WAS ESTIMATED FROM Z**2/A VALUES /14/.
REFERENCES
1) TAKAGI N. ET AL.: J. NUCL. SCI. TECHNOL., 27, 853 (1990).
2) TUTTLE R.J.: INDC(NDS)-107/G+SPECIAL, P.29 (1979),
3) BENEDETTI G. ET AL.: NUCL. SCI. ENG., 80, 379 (1982).
4) WALDO R. ET AL.: PHYS. REV., C23, 1113 (1981).
5) BRADY M.C. AND ENGLAND T.R.: NUCL. SCI. ENG., 103, 129(1989).
6) MANERO F. AND KONSHIN V.A.: AT. ENERGY REV.,10, 637 (1972).
7) HOWERTON R.J.: NUCL. SCI. ENG., 62, 438 (1977).
8) MUGHABGHAB S.F.: "NEUTRON CROSS SECTIONS, VOL.1, NEUTRON
RESONANCE PARAMETERS AND THERMAL CROSS SECTIONS , PART B,
Z=61-100", ACADEMIC PRESS (1984).
9) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
10) OHSAWA T. AND OHTA M.: J. NUCL. SCI. TECHNOL., 18, 408 (1981).
11) TOTH K.S.: NUCL. DATA SHEETS, 24, 263 (1978).
12) GILBERT A. AND CAMERON A.G.W.: CAN. J. PHYS., 43, 1446 (1965).
13) BEHRENS J.W. AND HOWERTON R.J: NUCL. SCI. ENG., 65, 464(1978).
14) SMITH A.B. ET AL.: ANL/NDM-50 (1979).
Back
|
