93-Np-239
93-NP-239 KYUSHU U.+ EVAL-MAR76 Y.KANDA, JENDL-CG
DIST-MAR02 REV3-FEB02 20020222
----JENDL-3.3 MATERIAL 9352
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
===========================================================
JENDL-3.2 data were automatically transformed to JENDL-3.3.
Interpolation of spectra: 22 (unit base interpolation)
(3,251) deleted, T-matrix of (4,2) deleted, and others.
===========================================================
HISTORY
76-03 THE EVALUATION FOR JENDL-1 WAS PERFORMED BY KANDA (KYUSHU
UNIV.) AND JENDL-1 COMPILATION GROUP. DETAILS ARE GIVEN
IN REF. /1/.
83-03 JENDL-1 DATA WERE ADOPTED FOR JENDL-2 AND EXTENDED TO 20
MEV. MF=5 WAS REVISED.
87-07 DATA FORMAT WAS CONVERTED INTO ENDF-5 FORMAT AND ADOPTED
TO JENDL-3.
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 DESCRIPTIVE DATA 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 ASSUMED TO
BE THE SAME AS THOSE OF NP-237 EVALUATED 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 NO RESONANCE PARAMETERS WERE GIVEN.
2200-M/SEC CROSS SECTIONS AND CALCULATED RESONANCE INTEGRALS.
2200 M/SEC RES. INTEG.
TOTAL 47.50 B -
ELASTIC 10.50 B -
FISSION 0.0 B 7.06 B
CAPTURE 37.00 B 445. B
MF=3 NEUTRON CROSS SECTIONS
BELOW 4.0 EV.
MT=1 TOTAL
SUM OF PARTIAL CROSS SECTIONS.
MT=2 ELASTIC SCATTERING
THE CONSTANT CROSS SECTION OF 10.5 BARNS WAS ASSUMED FROM
SIG=4*3.14*(0.147*A**(1/3))**2.
MT=18 FISSION
ASSUMED TO BE ZERO BARNS.
MT=102 CAPTURE
THE FORM OF 1/V WAS ASSUMED. THE 2200-M/SEC CROSS SECTION
WAS ADOPTED FROM THE EXPERIMENTAL DATA BY STOUGHTON AND
HALPERIN /8/.
ABOVE 4.0 EV.
MT=1 TOTAL
CALCULATED WITH OPTICAL AND STATISTICAL MODEL CODE CASTHY
/9/. OPTICAL POTENTIAL PARAMETERS WERE OBTAINED BY OHTA AND
MIYAMOTO /10/ BY USING THE TOTAL CROSS SECTION OF PU-239.
V = 45.87-0.2*EN, WI= 0.06, WS= 14.1, VSO= 7.3 (MEV)
R = 1.27 , RI= 1.27, RS=1.302, RSO= 1.27(FM)
A0= 0.652 , AI=0.315, AS= 0.98, ASO=0.652(FM)
MT=2 ELASTIC SCATTERING
CALCULATED WITH CASTHY /9/.
MT=4,51-58,91 INELASTIC SCATTERING
CALCULATED WITH CASTHY /9/. THE LEVEL SCHEME WAS ADOPTED
FROM NUCL. DATA SHEETS VOL.6.
NO. ENERGY(MEV) SPIN-PARITY
G.S. 0.0 5/2 +
1 0.03114 7/2 +
2 0.07112 9/2 +
3 0.07467 5/2 -
4 0.11766 11/2 +
5 0.1230 7/2 -
6 0.17305 9/2 -
7 0.2414 11/2 -
8 0.320 13/2 -
LEVELS ABOVE 430 KEV WERE ASSUMED TO OVERLAPPING. IN THE
CALCULATION THE CAPTURE, FISSION, (N,2N) AND (N,3N) CROSS
SECTIONS WERE CONSIDERED AS COMPETING PROCESSES.
MT=16,17 (N,2N) AND (N,3N)
CALCULATED WITH PEARLSTEIN'S METHOD /11/.
MT=18 FISSION
ESTIMATED FROM THE NP-237 FISSION CROSS SECTION BY NORMALI-
ZING WITH NEUTRON SEPARATION ENERGIES.
MT=102 CAPTURE
BELOW 100 KEV, THE CROSS SECTION WAS CALCULATED FROM
SIG = 435 / SQRT(EN) BARNS.
ABOVE 100 KEV, THE SHAPE OF THE EXPERIMENTAL DATA FOR NP-237
BY NAGLE ET AL. /12/ WAS ADOPTED AND NORMALIZED TO 1.4 BARNS
AT 100 KEV.
MT=251 MU-BAR
CALCULATED WITH CASTHY /9/.
MF=4 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=2 CALCULATED WITH CASTHY CODE /9/.
MT=51-58 ISOTROPIC IN THE CENTER-OF-MASS SYSTEM.
MT=16,17,18,91 ISOTROPIC IN THE LABORATORY SYSTEM.
MF=5 ENERGY DISTRIBUTIONS OF SECONDARY NEUTRONS
MT=16,17,91 EVAPORATION SPECTRUM.
MT=18 MAXWELLIAN FISSION SPECTRUM ESTIMATED FROM
Z**2/A SYSTEMATICS /13/.
REFERENCES
1) IGARASI S. ET AL.: JAERI 1261 (1979).
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) STOUGHTON R.W. AND HALPERIN J.: NUCL. SCI. ENG., 6, 100
(1959).
9) IGARASI S. AND FUKAHORI T.: JAERI 1321 (1991).
10) OHTA M. AND MIYAMOTO K.: J. NUCL. SCI. TECHNOL., 10, 583
(1973).
11) PEARLSTEIN S.: NUCL. SCI. ENG., 23, 238 (1965).
12) NAGEL R.J. ET AL.: 1971 KNOXVILLE CONF., 259 (1971).
13) SMITH A.B. ET AL.: ANL/NDM-50 (1979).