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24-Cr- 53 ORNL EVAL-NOV89 SHIBATA,HETRICK,DC & NM LARSON,FU
ORNL/TM10381,ENDF345 DIST-JAN09 20090105
----JEFF-311 MATERIAL 2434
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
*************************** JEFF-3.1.1 *************************
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** Original data taken from: JEFF-3.1 **
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***************************** JEFF-3.1 *************************
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** Original data taken from: JEFF-3.0 **
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***************************** JEFF-3.0 *************************
DATA TAKEN FROM :- ENDF/B-VI.3 (DIST-JUN90)
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REVISION 1 CHANGES
THE SECONDARY PARTICLE DISTRIBUTIONS FOR MF=6, MT=51-63 WERE
CORRECTED-TO-CENTER OF MASS, NOT LABORATORY COORDINATES.
THE ELASTIC TRANSFORMATION MATRIX WAS REMOVED.
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THIS WORK EMPLOYED NUCLEAR MODEL CODES INCLUDING THE
DISTORTED WAVE BORN APPROXIMATION (DWBA) PROGRAM DWUCK (1)
AND THE HAUSER-FESHBACH CODE TNG (2,3,4). THE TNG CODE PROVIDES
ENERGY AND ANGULAR DISTRIBUTIONS OF PARTICLES EMITTED IN THE
COMPOUND AND PRE-COMPOUND REACTIONS, ENSURES CONSISTENCY AMONG ALL
REACTIONS, AND MAINTAINS ENERGY BALANCE. DETAILS PERTINENT TO THE
CONTENTS OF THIS EVALUATION AND COMPARISONS OF CALCULATIONS
WITH EXPERIMENTAL DATA CAN BE FOUND IN REFERENCES (5) AND (6).
----- DESCRIPTION OF FILES
(MF-MT)
1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS.
2-151 RESONANCE PARAMETERS; USED TO PROVIDE THE TOTAL,
SCATTERING, AND CAPTURE CROSS SECTIONS FROM 1.E-5 EV TO
200 KEV. THE RESONANCE PARAMETERS ARE TAKEN PRIMARILY
FROM REF.(7) WITH HELP FROM BRUSEGAN ET AL. (PRIVATE
COMM., 1988). ADJUSTING OF REF. (7) PARAMETERS WAS DONE
AND A BACKGROUND FILE GIVEN IN 3/1 TO REPRODUCE DATA OF
REF. (9).
NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION
OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE
PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON
A FINER ENERGY GRID THAN GIVEN IN 4/2.
3-1 TOTAL CROSS SECTION; GIVEN BY RESONANCE PARAMETERS UP TO
200 KEV WITH NEGATIVE ENERGY RESONANCES ADJUSTED TO GIVE
MEASURED THERMAL SCATTERING AND CAPTURE CROSS SECTIONS.
A BACKGROUND FILE WAS REQUIRED FROM 20-200 KEV.
ABOVE 200 KEV, ISOTOPIC DATA USED TO 4.0 MEV (REF. (9))
AND FROM 4.0-20.0 MEV HIGH RESOLUTION
NAT CR TRANSMISSION MEASUREMENTS WERE USED
(D.C. LARSON, J.A. HARVEY, AND N.W. HILL, PRIVATE
COMM., 1988; DATA AVAILABLE AT NNDC).
3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY
SUBTRACTING THE NONELASTIC FROM THE TOTAL
3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22,
3-28, 3-102, 3-103, AND 3-107.
3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, ..
.., 3-63, AND 3-91
3-16 (N,2N) CROSS SECTIONS WERE CALCULATED BY THE TNG
CODE (2,3,4,5). NO DATA AVAILABLE; HOWEVER, SEE REF (6)
FOR COMPARISON TO NAT CR(N,2N) DATA.
3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG
CODE (2,3,4,5). NO DATA AVAILABLE.
3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG
CODE (2,3,4,5). SPARSE DATA AVAILABLE DISCREPANT.
3-51 TO 3-63 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE
FROM TNG (2,3,4,5) WHICH INCLUDES DIRECT INTERACTION
CROSS SECTIONS FROM DWUCK (1) CALCULATIONS. COMPARISONS
TO MEASURED DATA SHOWN IN (5).
3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG
CALCULATED). GUIDANCE FROM (N,XN) EMISSION DATA (6).
3-102 (N,G) CAPTURE CROSS SECTION; GIVEN BY RESONANCE PARAMETERS
UP TO 200 KEV AND FROM 200 KEV TO 20 MEV, TNG CALC'S
WERE USED BUT NORMALIZED TO MEASURED AVE. CAPTURE BETWEEN
50 KEV AND 200 KEV. TNG CALCULATIONS INCLUDED A PRE-
COMPOUND COMPONENT AND WEIGHTED CROSS SECTIONS FROM ALL
ISOTOPES OF CR GIVE 0.82 MB AT 14.5 MEV, IN AGREEMENT WITH
MEASUREMENT OF 0.75 MB FOR NAT CR.
3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG
CODE (2,3,4,5), BUT ADJUSTED BETWEEN EN OF 5.5 TO 10 MEV
TO FIT THE DATA OF SMITH ET AL. (8).
3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE
TNG CODE (2,3,4,5). NO DATA AVAILABLE.
4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR
ELASTIC SCATTERING ARE FROM ENDF/B-V.
IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY
THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE
PARAMETERS IN 2/151.
6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON AND 52CR RESIDUAL, AND ENERGY DEPENDENT YIELD
BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA
RAY; TNG CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR
EACH PRODUCT. ISOTROPY IS ASSUMED.
6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON, ALPHA, AND 49TI RESIDUAL, AND ENERGY DEPENDENT
YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE
GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN
FOR EACH PRODUCT. ISOTROPY IS ASSUMED.
6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE
NEUTRON AND 52V RESIDUAL, AND ENERGY DEPENDENT YIELD
BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA
RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR
EACH PRODUCT. ISOTROPY IS ASSUMED.
6-51 THROUGH 6-63 INELASTIC SCATTERING EXCITING LEVELS;
ASSUMED ISOTROPIC.
6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES
SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 53CR
RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG
CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; TNG
CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN
FOR EACH. ISOTROPY IS ASSUMED.
6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P
AND 53V RESIDUAL, AND ENERGY DEPENDENT YIELD BASED
ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY;
CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH
PRODUCT. ISOTROPY IS ASSUMED.
6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A
AND 50TI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED
ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY;
CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH
PRODUCT. ISOTROPY IS ASSUMED.
12-51 THROUGH 12-63 BRANCHING RATIOS FOR THE LEVELS, COMPILED
BY SHIBATA AND HETRICK (5), ARE GIVEN.
12-102 (N,G) CAPTURE; TNG CALCULATED.
14-51 THROUGH 14-58 AND 14-102 GAMMA RAY ANGULAR DISTRIBUTIONS
ASSUMED TO BE ISOTROPIC.
15-102 (N,G) CAPTURE; TNG CALCULATED.
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UNCERTAINTY FILES
AN LB=8 SECTION IS INCLUDED FOR ALL NON-DERIVED FILES AS
REQUIRED BY ENDF/B-VI.
33-1 UNCERTAINTIES ARE DERIVED FROM 1.E-5 TO 10 EV. FROM 10
EV TO 20 MEV THEY ARE EXPLICIT, USING LB=0,1 AND 8.
33-2 FROM 1.E-5 TO 10 EV, UNCERTAINTIES ARE EXPLICIT, BASED
UPON THERMAL UNCERTAINTY AND OTHER DATA. FROM 10 EV TO
20 MEV THE FILES ARE DERIVED.
33-3 FROM 1.E-5 TO 200 KEV UNCERTAINTIES ARE DERIVED. FROM 200
KEV TO 20 MEV UNCERTAINTIES ARE EXPLICIT, USING LB=1 AND 8
33-4 UNCERTAINTIES ARE ALL DERIVED.
33-16 UNCERTAINTIES FOR (N,2N) ARE EXPLICIT, ESTIMATED FROM TNG
33-22 UNCERTAINTIES FOR (N,NA) ARE EXPLICIT, ESTIMATED FROM TNG
33-28 UNCERTAINTIES FOR (N,NP) ARE EXPLICIT, ESTIMATED FROM TNG
33-51-91 UNCERTAINTIES FOR INELASTIC SCATTERING ARE EXPLICIT,
BASED ON DATA AND CALCULATION UNCERTAINTIES.
33-102 UNCERTAINTIES ARE EXPLICIT, BASED ON THERMAL DATA AT LOW
ENERGIES, AND CALCULATED RESULTS ABOVE 200 KEV.
33-103 UNCERTAINTIES ESTIMATED FROM TNG.
33-107 UNCERTAINTIES ESTIMATED FROM TNG.
REFERENCES:
(1) P.D. KUNZ, "DISTORTED WAVE CODE DWUCK72," UNIV. OF
COLORADO, UNPUBLISHED (1972).
(2) C.Y. FU, "A CONSISTENT NUCLEAR MODEL FOR COMPOUND AND
PRECOMPOUND REACTIONS WITH CONSERVATION OF ANGULAR
MOMENTUM," ORNL/TM-7042 (1980) AND NSE 100, 61 (1988).
(3) C.Y FU, "DEVELOPMENT AND APPLICATION OF MULTI-STEP
HAUSER-FESHBACH/PRE-EQUILIBRIUM MODEL THEORY," SYMP.
NEUTRON CROSS SECTIONS FROM 10 TO 50 MEV, UPTON, N.Y.,
MAY 12-14,1980, BNL-NCS-51425, P 675, BROOKHAVEN
NATIONAL LAB.
(4) K. SHIBATA AND C.Y. FU, "RECENT IMPROVEMENTS OF THE TNG
STATISTICAL MODEL CODE", ORNL/TM-10093 (AUGUST, 1986).
(5) K. SHIBATA AND D.M. HETRICK, "CALCULATED NEUTRON
-INDUCED CROSS SECTIONS FOR 53CR FROM 1 TO 20 MEV,"
ORNL/TM-10381, ENDF-345 (1987).
(6) D.M. HETRICK, C.Y. FU, AND D.C. LARSON, "CALCULATED NEUTRON
-INDUCED CROSS SECTIONS FOR 52CR FROM 1 TO 20 MEV AND
COMPARISONS WITH EXPERIMENT," ORNL/TM-10417,ENDF-346 (1987).
(7) A. BRUSEGAN, R. BUYL, F.CORVI, L. MEWISSEN, F.POORTMANS,
G. ROHR, R. SHELLEY, T. VAN DER VEEN, I. VAN MARCKE, "HIGH
RESOLUTION NEUTRON CAPTURE AND TOTAL CROSS SECTION
MEASUREMENTS OF 50CR, 52CR, AND 53CR," PROC. OF INT. CONF AT
SANTA FE, NM, PP. 633-640 (MAY 13-17, 1985).
(8) D.L. SMITH, J.W. MEADOWS, AND F.F. PORTA, NUCL. SCI. ENG.,
78(4), 420-424 (1981).
(9) J.A. HARVEY, PRIVATE COMMUNICATION OF ORELA 53CR+N DATA,1988.
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