ENTRY F1514 20241217 F151400000001 SUBENT F1514001 20241217 20250711 F151400100001 BIB 10 40 F151400100002 TITLE Measurement of cross-section of the 7Li(d,n)8Be F151400100003 reactions at the deuteron energies from 0.4 to 2.1 MeV F151400100004 AUTHOR (S.A.Meshchaninov,A.V.Krasilnikov,N.B.Rodionov, F151400100005 Yu.A.Kashchuk,S.Yu.Obudovsky,A.S.Dzhurik, F151400100006 T.M.Kormilitsyn,R.N.Rodionov,V.N.Amosov,G.E.Nemtsev, F151400100007 M.I.Bikchurina,T.A.Bykov,G.D.Verkhovod,D.A.Kasatov, F151400100008 Ya.A.Kolesnikov,G.M.Ostreinov,E.O.Sokolova, F151400100009 S.Yu.Taskaev) F151400100010 INSTITUTE (4RUSRUS) Institution Project Center ITER, State F151400100011 Atomic Energy Corporation Rosatom F151400100012 (4RUSSIB) Budker Institute of Nuclear Physics F151400100013 (4RUSNVU) Novosibirsk State University F151400100014 (4ZZZDUB) F151400100015 REFERENCE (J,PAN,87,769,2024) F151400100016 #doi:10.1134/S1063778824700789 F151400100017 FACILITY (VDGT,4RUSSIB) Vacuum insulated tandem accelerator F151400100018 DETECTOR Two radiometers of fast neutrons RBN-A1 with F151400100019 spectrometric diamond detectors are used. The AD-1 F151400100020 detector is manufactured from a single-crystal CVD F151400100021 plate with dimensions 4.5x4.5x0.5 mm3 (the contact F151400100022 area is 12.25 mm2). The B68 detector is manufactured F151400100023 from a single-crystal CVD film with dimensions F151400100024 4.0x4.0x0.09 mm3 (the contact area is 9 mm2). F151400100025 SAMPLE The lithium target was a copper disk 144 mm in F151400100026 diameter and 8 mm in thickness. The thickness of the F151400100027 lithium layer was 1.79+-0.07 mu-m. The content of F151400100028 lithium-7 was assumed to be 92.5%. F151400100029 ERR-ANALYS Standard deviation was 1-1.5%. F151400100030 (ERR-1) Uncertainty in the measurement of the lithium F151400100031 thickness F151400100032 (ERR-2,,4.3) Uncertainty of determining the sensitivityF151400100033 of detectors F151400100034 (ERR-3,,2.) Uncertainty of detector mounting F151400100035 (ERR-4) Uncertainty of determining the coefficient of F151400100036 attenuation of the monoenergetic neutron flux at F151400100037 passage through structural materials F151400100038 (ERR-5) Uncertainty of determining the density of F151400100039 atomic nuclei of lithium F151400100040 STATUS (APRVD) Entry was approved by Dr. S.Yu.Taskaev F151400100041 HISTORY (20241217C) F151400100042 ENDBIB 40 0 F151400100043 COMMON 4 3 F151400100044 ANG-ERR ERR-1 ERR-4 ERR-5 F151400100045 PER-CENT PER-CENT PER-CENT PER-CENT F151400100046 1. 4. 4. 1. F151400100047 ENDCOMMON 3 0 F151400100048 ENDSUBENT 47 0 F151400199999 SUBENT F1514002 20241217 20250711 F151400200001 BIB 4 8 F151400200002 REACTION (3-LI-7(D,N)4-BE-8,PAR,DA) F151400200003 FLAG (1.) RBN-A1-001 with detector AD-1 was used. F151400200004 (2.) RBN-A3-001 with detector B68 was used. F151400200005 ERR-ANALYS (ERR-S) Statistical error F151400200006 (ERR-T,,7.6) Total error F151400200007 (DATA-ERR) The uncertainty of determining the F151400200008 cross-section of the 12C(n,alpha0)8Be reaction F151400200009 STATUS (TABLE,,S.A.Meshchaninov+,J,PAN,87,769,2024) Table 4 F151400200010 ENDBIB 8 0 F151400200011 COMMON 1 3 F151400200012 E-LVL F151400200013 MEV F151400200014 0. F151400200015 ENDCOMMON 3 0 F151400200016 DATA 6 32 F151400200017 EN ANG DATA ERR-S DATA-ERR FLAG F151400200018 KEV ADEG MB/SR MB/SR PER-CENT NO-DIM F151400200019 333. 9. 0.12 0.02 6.3 1.F151400200020 333. 38. 0.40 0.06 6.3 2.F151400200021 441. 29. 0.57 0.03 6.4 1.F151400200022 441. 32. 0.67 0.13 6.4 2.F151400200023 760. 30. 3.28 0.10 6.4 1.F151400200024 760. 38. 1.86 0.14 6.4 2.F151400200025 864. 38. 1.53 0.13 6.6 2.F151400200026 864. 90. 1.73 0.08 6.6 1.F151400200027 962. 13. 1.64 0.16 6.4 2.F151400200028 962. 20. 1.74 0.04 6.4 1.F151400200029 1064. 13. 1.95 0.19 6.6 2.F151400200030 1064. 20. 1.96 0.05 6.6 1.F151400200031 1170. 13. 1.69 0.17 6.8 2.F151400200032 1170. 20. 1.87 0.05 6.8 1.F151400200033 1270. 13. 1.51 0.16 6.8 2.F151400200034 1270. 20. 1.96 0.05 6.8 1.F151400200035 1372. 13. 1.79 0.18 6.8 2.F151400200036 1372. 20. 2.06 0.05 6.8 1.F151400200037 1473. 13. 1.73 0.19 7.0 2.F151400200038 1473. 20. 2.17 0.06 7.0 1.F151400200039 1573. 13. 1.49 0.18 7.0 2.F151400200040 1573. 20. 2.37 0.06 7.0 1.F151400200041 1674. 13. 1.90 0.21 7.0 2.F151400200042 1674. 20. 2.55 0.06 7.0 1.F151400200043 1776. 13. 2.01 0.22 7.0 2.F151400200044 1776. 20. 2.50 0.06 7.0 1.F151400200045 1877. 13. 1.62 0.19 6.8 2.F151400200046 1877. 20. 2.38 0.06 6.8 1.F151400200047 1977. 13. 2.15 0.22 6.8 2.F151400200048 1977. 20. 2.35 0.06 6.8 1.F151400200049 2078. 13. 2.01 0.21 6.9 2.F151400200050 2078. 20. 2.27 0.06 6.9 1.F151400200051 ENDDATA 34 0 F151400200052 ENDSUBENT 51 0 F151400299999 SUBENT F1514003 20241217 20250711 F151400300001 BIB 3 6 F151400300002 REACTION (3-LI-7(D,N)4-BE-8,PAR,SIG) F151400300003 ERR-ANALYS (ERR-S) Statistical error F151400300004 (ERR-T,,7.6) Total error F151400300005 (DATA-ERR) The uncertainty of determining the F151400300006 cross-section of the 12C(n,alpha0)8Be reaction F151400300007 STATUS (TABLE,,S.A.Meshchaninov+,J,PAN,87,769,2024) Table 5 F151400300008 ENDBIB 6 0 F151400300009 COMMON 1 3 F151400300010 E-LVL F151400300011 MEV F151400300012 0. F151400300013 ENDCOMMON 3 0 F151400300014 DATA 5 16 F151400300015 EN EN-ERR DATA ERR-S DATA-ERR F151400300016 KEV KEV MB MB MB F151400300017 333. 72. 1.64 15.7 6.3 F151400300018 441. 63. 7.71 5.1 6.4 F151400300019 760. 47. 34.16 3.2 6.4 F151400300020 864. 43. 27.77 4.6 6.6 F151400300021 962. 41. 18.23 2.6 6.4 F151400300022 1064. 38. 20.44 2.5 6.6 F151400300023 1170. 37. 19.91 2.6 6.8 F151400300024 1270. 34. 22.27 2.5 6.8 F151400300025 1372. 32. 23.60 2.5 6.8 F151400300026 1473. 31. 23.96 2.6 7.0 F151400300027 1573. 29. 24.97 2.6 7.0 F151400300028 1674. 28. 25.83 2.5 7.0 F151400300029 1776. 27. 24.57 2.6 7.0 F151400300030 1877. 26. 22.34 2.6 6.8 F151400300031 1977. 25. 20.51 2.6 6.8 F151400300032 2078. 24. 21.24 2.6 6.9 F151400300033 ENDDATA 18 0 F151400300034 ENDSUBENT 33 0 F151400399999 SUBENT F1514004 20241217 20250711 F151400400001 BIB 3 10 F151400400002 REACTION (3-LI-7(D,N)4-BE-8,PAR,DA) F151400400003 ERR-ANALYS (ERR-T,,26.1) Total error F151400400004 (DATA-ERR1,,25.) The sum of uncertainty of determining F151400400005 the cross-section of nuclear neutron reactions by F151400400006 carbon from the ENDF/B-VIII.0 database, approximation F151400400007 error F151400400008 (DATA-ERR2) The square root of the sum of squares of F151400400009 the statistical error and the uncertainty of F151400400010 background function F151400400011 STATUS (TABLE,,S.A.Meshchaninov+,J,PAN,87,769,2024) Table 7 F151400400012 ENDBIB 10 0 F151400400013 COMMON 2 3 F151400400014 E-LVL E-LVL-ERR F151400400015 MEV MEV F151400400016 2.88 0.13 F151400400017 ENDCOMMON 3 0 F151400400018 DATA 5 14 F151400400019 EN EN-ERR ANG DATA DATA-ERR2 F151400400020 KEV KEV ADEG MB/SR MB/SR F151400400021 760. 47. 30. 0.33 0.28 F151400400022 864. 43. 90. 2.00 0.46 F151400400023 962. 41. 20. 2.31 0.45 F151400400024 1064. 38. 20. 4.43 1.03 F151400400025 1170. 37. 20. 2.28 0.66 F151400400026 1270. 34. 20. 1.91 0.47 F151400400027 1372. 32. 20. 1.43 0.43 F151400400028 1473. 31. 20. 1.27 0.24 F151400400029 1573. 29. 20. 1.30 0.46 F151400400030 1674. 28. 20. 1.45 0.44 F151400400031 1776. 27. 20. 1.99 0.65 F151400400032 1877. 26. 20. 1.71 0.84 F151400400033 1977. 25. 20. 1.73 0.46 F151400400034 2078. 24. 20. 1.37 0.23 F151400400035 ENDDATA 16 0 F151400400036 ENDSUBENT 35 0 F151400499999 SUBENT F1514005 20241217 20250711 F151400500001 BIB 3 6 F151400500002 REACTION (3-LI-7(D,N)4-BE-8,PAR,SIG) F151400500003 ERR-ANALYS (ERR-T,,26.1) Total error F151400500004 (DATA-ERR) The square root of the sum of squares of F151400500005 the statistical error and the uncertainty of backgroundF151400500006 function F151400500007 STATUS (TABLE,,S.A.Meshchaninov+,J,PAN,87,769,2024) Table 7 F151400500008 ENDBIB 6 0 F151400500009 COMMON 2 3 F151400500010 E-LVL E-LVL-ERR F151400500011 MEV MEV F151400500012 2.88 0.13 F151400500013 ENDCOMMON 3 0 F151400500014 DATA 4 14 F151400500015 EN EN-ERR DATA DATA-ERR F151400500016 KEV KEV MB MB F151400500017 760. 47. 3.91 3.3 F151400500018 864. 43. 25.1 5.8 F151400500019 962. 41. 26.9 5.2 F151400500020 1064. 38. 51.8 11.9 F151400500021 1170. 37. 26.3 7.6 F151400500022 1270. 34. 22.1 5.4 F151400500023 1372. 32. 16.4 4.9 F151400500024 1473. 31. 14.6 2.7 F151400500025 1573. 29. 14.8 5.2 F151400500026 1674. 28. 16.5 5.1 F151400500027 1776. 27. 22.6 7.4 F151400500028 1877. 26. 19.4 9.5 F151400500029 1977. 25. 19.6 5.2 F151400500030 2078. 24. 15.5 2.5 F151400500031 ENDDATA 16 0 F151400500032 ENDSUBENT 31 0 F151400599999 ENDENTRY 5 0 F151499999999