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3.608000+4 7.922980+1 1 0 2 0
0.000000+0 0.000000+0 0 0 0 6
1.000000+0 2.000000+7 0 0 10 31
0.000000+0 0.000000+0 0 0 78 1
36-Kr- 80 NEA RCOM-JUL82 SCIENTIFIC CO-ORDINATION GROUP
DIST-MAY05 REV1-MAY05 20050504
----JEFF-31 MATERIAL 3631
-----INCIDENT NEUTRON DATA
------ENDF-6 FORMAT
***************************** JEFF-3.1 *************************
** **
** Original data taken from: JEFF-3.0 **
** **
******************************************************************
***************************** JEFF-3.0 ***********************
DATA TAKEN FROM :- JEF-2.2 (DIST-JAN92)
******************************************************************
* JEF-2 *
* DATA WERE TAKEN FROM ENDF/B-V(MAT=1331). *
******************************************************************
* 23-NOV-84: NONELASTIC CROSS SECTION DELETED
* 3-JAN-84: RESONANCE PARAM. CHANGED TO ORIGINAL SINGLE-LEVEL
* 4-MAR-85: Q-VALUE FOR MT=107 CORRECTED
* 16-OCT87 : CHANGE OF THE FLAG FROM SINGLE LEVEL TO MULTI LEVEL
* BREIT-WIGNER RESONANCE PARAMETERS
* 27-APR-89: MISSING CHARGE PARTICLE PRODUCTION DATA INCLUDED
* FROM REAC-ECN-4 LIBRARY
******************************************************************
BNL EVAL-APR78 A.PRINCE
DIST-APR79 REV1-DEC78 790105
ABUNDANCE=2.27 PERCENT OF NATURAL ELEMENT
RESOLVED RESONANCE REGION (1.0E-05 EV TO 1.0 KEV)
RESONANCE PARAMETERS BASED ON DATA FROM REFS.1 TO 3
CALCULATED 0.0253 EV CAPTURE CROSS SECTION =11.74 B
EXPTL AND RECOMMENDED VALUES OF THERMAL CAPTURE CROSS SECTION
14.0 +/-1.5 B REF 2
11.3 +1-0.4 B REF 4
15.6 +/-2.8 B REF 5
11.5 +/-0.6 B REF 6
11.5 +/-0.5 B REF 7
12.6 B REF 8
CALCULATED RES. INTEGRAL(0.5 EV CUT-OFF)=68.6 B
EXPTL AND RECOMMENDED VALUES OF RES. INTEGRAL
56.0 +/-7.0 B REF 3
56.1 +/-5.6 B REF 2
56.1 +/-2.8 B REF 4
POTENTIAL SCATT. CROSS SECTION =6.2 B(REF 9)
=7.5 +/-.13 B (NAT KR) REF 2
FAST NEUTRON CROSS SECTIONS (1.0 KEV TO 20.0 MEV)
GENERAL DESCRIPTION
TOTAL AND ELASTIC CROSS SECTIONS CALCULATED WITH ABACUS OPTICAL
MODEL CODE (REF.10)
THE INELASTIC,CAPTURE,N,P AND N-4HE CROSS SECTIONS CALCULATED WITH
CODE CERBERO (REF.11)
MT=16,104,105,106 WERE OBTAINED FROM CODE FASCRO (REF.12)
ANGULAR DISTRIBUTION DATA WAS ANALYZED WITH CODE CHAD (REF.13)
THE BINDING ENERGIES AND THRESHOLDS ARE BASED ON REF.14
SHELL AND PAIRING CORRECTIONS WERE TAKEN FROM REF.15
THE NUCLEAR TEMPERATURES IN FILE 5 WERE CALCULATED ACCORDING TO
REF.16
REFERENCES
1-D.P.MANN AND W.W.WATSON,PHYS.REV.116(1959)1516
2-BNL 325 VOL1(3RD.EDITION)1973
3-R.C.BLOCK ET AL, INTL. CONF. HARWELL (1978)
4-J.G.BRADLEY AND W.H.JOHNSON, NSE.47(1972)151
5-I.R.BARABANOV ET AL, J.E.T.P. LETTERS VOL.15,NO.11(1972)456
6-N.E.HOLDEN AND F.W.WALKER, G.E. CHART OF NUCLIDES (11TH.ED)1972
7-N.E.HOLDEN (BNL) PR1.COMM.1978
8-F.W.WALKER ET AL G.E. CHART OF NUCLIDES (12 TH.ED)1977
9-D.C.RORER ET AL,NUCL.PHYS.A120(1968)329
10-ABACUS,E.H.AUERBACH,BNL 6562(UNPUBL)1964
11-CERBERO-2,F.FABBRI ET AL,CNEN RPT.RT/FI(77)6,1977
12-FASCRO,S.PEARLSTEIN,BNL(UNPUBL)
13-CHAD,R.F.BERLAND,NAA-SR-11231(1965)
14-A.H.WAPSTRA AND N.B.GOVE,NUCL.DATA TABLES 9A(1971)
15-J.L.COOK ET AL,AUST.J.PHYS.20(1967)477
16-A.GILBERT AND A.G.W.CAMERON,CAN.J.PHYS.43(1965)1446
1 451 83
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