n 1 - IAEA Nuclear Data Services

More documents

Recommendations

Info

1 33 o. O O t— bJ in co 10 o rt: 0.05 0.10 0.15 0.20 0.25 0.30 *0.3S 0.40 0.45 0-50 .0.55 ' NEUTRON ENERGY. MEV Fig. 2. The Version V s Ll(n,t)' l He cross section from 50 to 550 keV. The dashed curve ia ENDF/B-IV; the experimental data are from references 20-22, 32-34. Hr CM Oo I
- 36 - SUMMARY DOCUMENTATION FOR 10 B by G. M. Hale, L. Stewart, and P. G. Young Los Alamos.Scientific Laboratory Los Alamos, New Mexico I. SUMMARY * ' 5-B-10 MAT 1305 All cross sections below a neutron energy of 1.5 MeV except the (n,p) and (n,t) reactions were revised for the Version V evaluation of B (MAT 1305). The data above 1.5 MeV were carried over from ENDF/B—IV. Other changes to the file include the addition of evaluated cross sections and secondary gamma-ray spectra from tha ao B(n,Y) il B reaction, as well as covariance data for cross sections below 1.5 MeV. Except for the covariance file, the evaluated data cover the energy range from 10~ s eV to 20 MeV. Partial documentation is provided in LA-6472-PR (1976) and LA-6518-MS (1976). II.' STACTARDS -DATA • . The l0 B(n,a) 7 Li and 10 B(n,ouY) 7 Li reactions are neutron standards at energies below 100 keV. The major reactions below 1 MeV were obtained for the Ver- . slon V evaluation from multichannel, multilevel. R-matrix analyses of reactions in-the ll B system, similar to those from which the Version IV evaluation were taken. New data have becoae available since Version IV was released and most of this new experimental information has been incorporated into the present analyses. We have added Spencer's measurements of Oj (Sp73) and Sealock's 10 3(n,a^) angular distributions (Se76) to the data set chat was analyzed for Version IV. In addition, we have replaced Friesenhahn's integrated (n,a^) cross section with the recent measurements of' Schrack et al. (both with GeLi and Nal detectors) at. NBS (Sc76), and have deleted Friesenhahn's total (n,o) cross section from the data set. The resulting fit to the (n,cQ and (n,a Y) data is shown in Figs. 1 and 2, respectively. The integrated 10 3(n,a) cross section has changed negligibly from the Version IV results ac energies below 200 keV. At higher energies, however, the (n.oc) cross section has dropped significantly'in response to the new NBS data. Unfortunately, the rest of the data in the analysis do not seem particularly sensitive to such changes in the (n,o) cross section, with the result that our calculated cross section must be considered quite uncertain at energies above - 300 keV.
Page 1 and 2: INTERNATIONAL ATOMIC ENERGY AGENCY
Page 3 and 4: FORMAT - 2 - The data format of END
Page 5 and 6: BNL LASL ORNL Nuclide, Mat. No. Ene
Page 7 and 8: Covariance Nuclide, Mat. No. Energy
Page 9 and 10: Quantity (Data type) Covariance Not
Page 11 and 12: - 10 - File 4 A simplified format u
Page 13 and 14: - 12 - 1-H-l MAT 1301 Unfortunately
Page 15 and 16: REFERENCES - 14 - File 14. Gamma Ra
Page 17 and 18: - 16 - 1-H-l MAT 1301 29. W. Sleato
Page 19 and 20: CO X CD O LJ CO to-, oo CO 2 CD O U
Page 21 and 22: 01 co to
Page 23 and 24: I. SUMMARY - HS*«I - 22 - SUMMARY
Page 25 and 26: - -24 - 2-He-3 MAT 1146 MT-251. Ave
Page 27 and 28: '(Uln.pIT MACKUN.ORM.* 1963 * GIBBO
Page 29 and 30: - 28 - 3-Li-6 •!AT 1303 Approxima
Page 31 and 32: MT-102. (n,Y) Cross Sections - 30 -
Page 33 and 34: REFERENCES - 32 - File 14. Gamma-Ra
Page 35: K K LU r: i CD * K UJ m to oCNI O O
Page 39 and 40: Wl>51-61. Inelastic Cross Sections
Page 41 and 42: File 12. Gamma Ray Multiplicities M
Page 43 and 44: - 42 - Ne70 D. 0. Nellis et al., Ph
Page 45 and 46: in x M ;> \u zri en in M M UJ X to
Page 47 and 48: MAT 1306 - 46 - File 3, MT«2. Elas
Page 49 and 50: 6-C-O MAT 1306 -48 - File 4, MT*52.
Page 51 and 52: 6-C-O MAT 1306 24. C. A. Kelsey et
Page 53 and 54: 6-C-O HAT 1306 -52 - Covariance Fil
Page 55 and 56: 79-Au-197 MAT 1379 - 54 - available
Page 57 and 58: 79-AU-197 MAT 1379 -56 - were obtai
Page 59 and 60: ,79-Au-197 HAT 1379 -58 - file as v
Page 61 and 62: 79-AU-197 MAT 1379 - 60 - REFERENCE
Page 63 and 64: 79-AU-197 MAT 1379 - 62 - 29. A.E.
Page 65 and 66: 92-0-235 MAT 1395 3. File 2 - 64 -
Page 67 and 68: 92-U-235 MAT 1395 File 8 (cont'd) -
Page 69 and 70: - 68 - BNL-NCS-51184 (ENDF-248) UC-
Page 71 and 72: 1.0- Introduction - 70 - Table of C
Page 73 and 74: 11m nmitron »nid gumma-ray product
Page 75 and 76: However, in carrying out this merge
Page 77 and 78: . .im |-.i ii'il to tin' nvcrARit l
Page 79 and 80: l' 1 ; 0 - 240.0 b-eV. These data v
Page 81 and 82: Hi* ni|itiirn crnii* in-ctlnn ntirt
Page 83 and 84: 4.0 KvnInation of 0 . j, 23!) (eval
Page 85 and 86: References . . .... 1. L. Stewart,
Page 87 and 88:
55. V.C. Ne»terov, B. Hurpelaov, L
Page 89 and 90:
Table HI (cont.) Input Data for the
Page 91 and 92:
Table III (Cont'd) Input Data for t
Page 93 and 94:
Author Cwin Czirr ORHL-RPI Haaaon W
Page 95 and 96:
Tnble VII 235, Average U Finion Cro
Page 97 and 98:
100 200 300 ri(ur« I. lions, OBHl.
Page 99 and 100:
V 3.4 3.2 3.0 2.* 2.« A 2.4 2.0 1.
Page 101 and 102:
2.6 2.5 2.4 2.3- 2.2 2.1 1.9 1.8 1.
Page 103 and 104:
2.8 2.7 2'6 2.4 2.2 2.0 1.8 1.6 1.4
Page 105:
- 104 - REFERENCE GUIDELINES FOR EN
show all

n 1 - IAEA Nuclear Data Services

Create successful ePaper yourself

Delete template?

Save as template?