93-Np-237
93-NP-237 JAERI EVAL-Jan01 T.Nakagawa, O.Iwamoto
JAERI-R 2001-059 DIST-MAR02 REV4-JUL01 20010730
----JENDL-3.3 MATERIAL 9346
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
HISTORY
79-03 NEW EVALUATION WAS MADE BY N.WACHI AND Y.KANDA (KYUSHU
UNIVERSITY), AND Y.KIKUCHI (JAERI).
87-11 (N,2N), (N,3N) AND FISSION CROSS SECTIONS WERE RE-EVALUATED
IN THE ENERGY RANGE ABOVE 100 KEV BY Y.UENOHARA AND Y.KANDA
(KYUSHU UNIVERSITY).
88-01 COMPILED BY T.NAKAGAWA (JAERI).
MODIFIED QUANTITIES : (1,452), (1,456), (3,2), (3,16)
(3,17) AND (3,18)
89-02 FP YIELDS WERE TAKEN FROM JNDC FP DECAY FILE VERSION-2.
89-03 (N,2N) REACTION CROSS SECTION WAS MODIFIED.
93-08 JENDL-3.2.
(2,151), (3,18), (8,16) and (9,16) MODIFIED BY T.NAKAGAWA
(NDC/JAERI)
01-01 JENDL-3.3
Reevaluated and compiled by T.Nakagawa /1/
***** MODIFIED PARTS FROM JENDL-3.2 ********************
All except (3,16)
***********************************************************
MF=1 General Information
MT=451 Descriptive data and directory records
MT=452 Number of neutrons per fission
Sum of MT's= 455 and 456
MT=455 Delayed neutron data
Nu-d was based on the experimental data of Saleh et al./2/,
Charlton et al./3/, Piksaikin et al./4/ and Zeinalov et
al./5/ Decay constants were detemined from the experimental
data of Piksaikin et al. /4/.
MT=456 Number of prompt neutrons per fission
Based on the experimental data of Veeser /6/, Frehaut et
al. /7/, Malinovskii et al. /8/, Boikov et al. /9/,
and recommended data of Mughabghab /10/.
MF=2 Resonance Parameters
MT=151 Resolved and unresolved resonance parameters
1) Resolved resonance parameters for MLBW formula (below 500 eV)
Neutron and capture widths: Gressier et al. /11/ and
Auchampaugh et al. /12/
Fission width: Borzakov et al./13/, Dermendjiev et al.
/14/ and Auchampaugh et al. /12/
Parameters of the -0.56- and 0.49-eV resonance were
adjusted to reproduce thermal fission and capture cross
sections.
Scattering radius of 10.5 fm to reproduce the thermal total
cross section calculated from Gressier et al.'s parameters.
2) Unresolved resonance parameters (500 eV - 35 keV)
The average resonance parameters were determined with ASREP
/15/ to reproduce average cross sections:
total: Auchampaugh et al. /12/
fission: Yamanaka et al. /16/, Iwasaki et al./17/
capture: Weston and Todd /18/
Thermal cross sections and resonance integrals
-------------------------------------------------------
0.0253 eV reson. integ.
-------------------------------------------------------
total 175.79
elastic 14.06
fission 0.0204 6.90
capture 161.71 657
-------------------------------------------------------
MF=3 Neutron Cross Sections
MT= 1 Total cross section
Evaluation by Ignatyuk et al./19/ was adopted. Their data
reproduce well the experimental data of Kornilov et al./20/
and Auchampaugh et al./12/
MT= 2 Elastic scattering cross section
Calculated as (total - sum ofpartiacl cross sections)
MT=4, 51-82,91 Inelastic scattering cross sections
Evaluation by Ignatyuk et al./19/ was adopted.
MT=16 (n,2n) reaction cross section
The same as JENDL-3.2.
[Comment for JENDL-3.2]
FOR JENDL-2, DATA WERE CALCULATED WITH THE EVAPORATION
MODEL OF SEGEV+/21/. THE DATA FOR JENDL-3 WERE EVALUATED
BY FITTING TO THE FOLLOWING EXPERIMENTAL DATA.
PERKIN+ /22/, LANDRUM+ /23/, LINDKE+ /24/,
FORT+ /25/, GROMOVA+ /26/ AND KORNILOV+ /27/.
THE DATA OF JENDL-2 WERE USED AS PRIOR VALUES, AND 50%
FRACTIONAL STANDARD DEVIATIONS WERE ASSIGNED TO THEM.
MT=17, 37 (n,3n), (n,4n) recation cross sections
Evaluation by Ignatyuk et al./19/ was adopted.
MT=18 Fission cross section
Based on the experimental data:
Brown+ /28/, Jiacoletti+ /29/, Kobayashi+ /30/,
Plattard+ /31/, Alkhazov+ /32,33,34/, Grady+ /35/,
Cance+ /36/, Meadows+ /37,38/, Wu+ /39/, Zasadny+ /40/,
Garlea+ /41/, Gul+ /42/, Merla+ /43/, Behrens+ /44/,
Goverdovskij+ /45/, Kanda+ /46/, Terayama+ /47/,
Desdin+ /48/, Iwasaki+ /17/, Kuprijanov+ /49/,
Kovalenko+ /50/.
MT=102 Capture cross section
Evaluation by Ignatyuk et al./19/ was adopted.
MF=4 Angular Distributions of Secondary Neutrons
MT=2,51-82
ENDF/B-VI was adopted.
note: Data of MF=81 at 16 MeV were deleted because of
nagative distributions.
MF=5 Energy Distributions of Secondary Neutrons
MT=18
Maxwellian distributions were assumed. Temperature was
based on Baba /51/ and Boikov et al. /9/.
MT=455
Taken from Brady and England /52/.
MF=6 Energy-Angle Distrubutions
MT=16, 17, 37, 91
ENDF/B-VI was adopted.
MF=8 Radioactive Decay
MT=16
Decay data of Np-236: taken from Table of isotopes /53/
MF=9 Multiplicities for Production of Radioactive Nuclides
MT=16
Meta-stable state (T-1/2 =22.5H) production was assumed to
be 75 %.
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