ENTRY C0921 20220629 C092100000001 SUBENT C0921001 20220629 20231011 C092100100001 BIB 8 20 C092100100002 TITLE Equilibrium and Nonequilibrium Contributions to the C092100100003 (p,n) Cross Sections of Y, Nb, and Ta C092100100004 AUTHOR (S.M.Grimes,J.D.Anderson,B.A.Pohl,J.W.McClure,C.Wong) C092100100005 REFERENCE (J,PR/C,4,607,1971) C092100100006 #doi:10.1103/PhysRevC.4.607 C092100100007 INSTITUTE (1USALRL) C092100100008 FACILITY (CYCLO,1USALRL) C092100100009 DETECTOR (SCIN) NE213 scintillators. C092100100010 METHOD (TOF,PSD) 10.8-m flight path. A linear bias C092100100011 eliminated pulses produced by recoil protons with C092100100012 energies less than 1.6 MeV and gamma-produced C092100100013 background was reduced by utilizing pulse-shape C092100100014 discrimination. C092100100015 HISTORY (20030604C) VM C092100100016 (20220629A) BP: Updated entry, added doi and C092100100017 parametrized equilibrium and nonequilibrium cross C092100100018 sections in subentries 5-10, deleted subentries 3-4 C092100100019 (unobtainable data) per an NRDC decision for data C092100100020 sets that were published before 2000 (C32 of WP2022- C092100100021 01). C092100100022 ENDBIB 20 0 C092100100023 NOCOMMON 0 0 C092100100024 ENDSUBENT 23 0 C092100199999 SUBENT C0921002 20220629 20231011 C092100200001 BIB 4 7 C092100200002 REACTION (39-Y-89(P,X)0-NN-1,,DA/DE) C092100200003 ERR-ANALYS (ERR-S) Statistical uncertainty given. C092100200004 COMMENT Compiler's comment: I'm not aware of Walker curves. A C092100200005 135 degree data set is shown in Fig. 1 of C092100200006 J,PR/C,4,607,1971. C092100200007 STATUS (CURVE) Data read from Walker curves. Data measured C092100200008 at other energies and angles not available. C092100200009 ENDBIB 7 0 C092100200010 COMMON 1 3 C092100200011 EN C092100200012 MEV C092100200013 14.8 C092100200014 ENDCOMMON 3 0 C092100200015 DATA 4 86 C092100200016 ANG E DATA ERR-S C092100200017 ADEG MEV MB/SR/MEV MB/SR/MEV C092100200018 15. 3.7 8.5 0.8 C092100200019 15. 3.8 6.5 C092100200020 15. 4.1 5.5 C092100200021 15. 4.3 5.1 C092100200022 15. 4.5 4.0 C092100200023 15. 4.7 3.7 C092100200024 15. 4.9 3.2 C092100200025 15. 5.1 2.9 C092100200026 15. 5.3 2.4 C092100200027 15. 5.5 2.3 C092100200028 15. 5.7 2.3 C092100200029 15. 5.9 1.8 C092100200030 15. 6.1 1.9 C092100200031 15. 6.3 1.8 C092100200032 15. 6.5 1.5 C092100200033 15. 6.7 1.4 C092100200034 15. 6.9 0.95 C092100200035 15. 7.1 0.81 C092100200036 15. 7.3 0.83 C092100200037 15. 7.5 0.95 C092100200038 15. 7.7 1.1 C092100200039 15. 7.9 1.3 C092100200040 15. 8.1 1.2 C092100200041 15. 8.3 0.85 C092100200042 15. 8.5 0.72 C092100200043 15. 8.7 0.92 C092100200044 15. 8.9 0.65 C092100200045 15. 9.1 0.45 C092100200046 15. 9.3 0.20 C092100200047 15. 9.6 0.15 C092100200048 15. 9.7 0.13 C092100200049 15. 10.0 0.18 C092100200050 15. 10.2 0.20 C092100200051 15. 10.3 0.25 C092100200052 15. 10.4 0.32 C092100200053 15. 10.6 0.21 C092100200054 15. 10.7 0.19 C092100200055 15. 10.8 0.075 0.035 C092100200056 15. 11.0 0.11 C092100200057 15. 11.2 0.12 C092100200058 15. 11.3 0.68 C092100200059 15. 11.6 0.43 C092100200060 15. 11.7 0.23 C092100200061 135. 2.1 33. C092100200062 135. 2.3 27. C092100200063 135. 2.5 21. C092100200064 135. 2.7 20. C092100200065 135. 3.0 15. C092100200066 135. 3.2 13. C092100200067 135. 3.3 10. C092100200068 135. 3.5 8.0 C092100200069 135. 3.7 6.5 C092100200070 135. 3.9 5.2 C092100200071 135. 4.1 4.5 C092100200072 135. 4.3 4.0 C092100200073 135. 4.7 3.3 C092100200074 135. 4.9 1.4 C092100200075 135. 5.1 1.8 C092100200076 135. 5.3 1.5 C092100200077 135. 5.5 1.3 C092100200078 135. 5.7 1.3 C092100200079 135. 5.8 1.0 C092100200080 135. 6.0 0.95 0.015 C092100200081 135. 6.3 0.95 C092100200082 135. 6.4 0.70 C092100200083 135. 6.7 0.65 C092100200084 135. 6.8 0.40 C092100200085 135. 7.1 0.52 0.10 C092100200086 135. 7.3 0.40 C092100200087 135. 7.5 0.52 C092100200088 135. 7.7 0.45 C092100200089 135. 7.9 0.36 C092100200090 135. 8.1 0.14 C092100200091 135. 8.3 0.30 C092100200092 135. 8.6 0.33 C092100200093 135. 8.7 0.16 C092100200094 135. 8.9 0.05 C092100200095 135. 9.1 0.04 C092100200096 135. 9.3 0.035 C092100200097 135. 9.5 0.022 C092100200098 135. 9.7 0.018 C092100200099 135. 10.0 0.015 C092100200100 135. 10.2 0.035 0.025 C092100200101 135. 10.4 0.022 C092100200102 135. 10.6 0.046 C092100200103 135. 10.8 0.021 C092100200104 ENDDATA 88 0 C092100200105 ENDSUBENT 104 0 C092100299999 NOSUBENT C0921003 20220629 20231011 C092100300001 NOSUBENT C0921004 20220629 20231011 C092100400001 SUBENT C0921005 20220805 20231011 C092100500001 BIB 5 16 C092100500002 REACTION 1(39-Y-89(P,N)40-ZR-89,,SIG,,MSC,DERIV) C092100500003 Calculated equilibrium cross sections assuming C092100500004 spectra parametrization sigma/epsilon = A*exp(U/T) + C092100500005 B*U**n, where U is nuclear temperature. C092100500006 2(39-Y-89(P,3N)40-ZR-87,,SIG,,MSC,DERIV) C092100500007 Calculated equilibrium cross sections assuming C092100500008 spectra parametrization sigma/epsilon = A*exp(U/T) + C092100500009 B*U**n, where U is nuclear temperature. C092100500010 ANALYSIS The nuclear temperatures determined at lower energy C092100500011 were used in a constant-temperature level density form C092100500012 for rho(U) and the best-fit values of A and B were C092100500013 calculated for n=0-6. C092100500014 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties C092100500015 STATUS (DEP,C0921002) C092100500016 (TABLE) Table IV, page 616 of J,PR/C,4,607,1971. C092100500017 HISTORY (20220629C) BP C092100500018 ENDBIB 16 0 C092100500019 NOCOMMON 0 0 C092100500020 DATA 5 3 C092100500021 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 C092100500022 MEV MB MB MB MB C092100500023 10.0 800.0 150.0 C092100500024 12.3 1250.0 200.0 C092100500025 14.8 540.0 150.0 1620.0 400.0 C092100500026 ENDDATA 5 0 C092100500027 ENDSUBENT 26 0 C092100599999 SUBENT C0921006 20220805 20231011 C092100600001 BIB 5 16 C092100600002 REACTION 1(39-Y-89(P,N)40-ZR-89,,SIG,,MSC,DERIV) C092100600003 Calculated equilibrium cross sections assuming C092100600004 spectra parametrization sigma/epsilon = A*exp(U/T) + C092100600005 B*U**n, where U is nuclear temperature. C092100600006 2(39-Y-89(P,3N)40-ZR-87,,SIG,,MSC,DERIV) C092100600007 Calculated equilibrium cross sections assuming C092100600008 spectra parametrization sigma/epsilon = A*exp(U/T) + C092100600009 B*U**n, where U is nuclear temperature. C092100600010 ANALYSIS The nuclear temperatures determined at lower energy C092100600011 were used in a constant-temperature level density form C092100600012 for rho(U) and the best-fit values of A and B were C092100600013 calculated for n=0-6. C092100600014 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties C092100600015 STATUS (DEP,C0921002) C092100600016 (TABLE) Table IV, page 616 of J,PR/C,4,607,1971. C092100600017 HISTORY (20220629C) BP C092100600018 ENDBIB 16 0 C092100600019 NOCOMMON 0 0 C092100600020 DATA 5 2 C092100600021 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 C092100600022 MEV MB MB MB MB C092100600023 12.3 67.0 20.0 C092100600024 14.8 88.0 30.0 100.0 40.0 C092100600025 ENDDATA 4 0 C092100600026 ENDSUBENT 25 0 C092100699999 SUBENT C0921007 20220805 20231011 C092100700001 BIB 5 15 C092100700002 REACTION 1(41-NB-93(P,N)42-MO-93,,SIG,,MSC,DERIV) C092100700003 Calculated equilibrium cross sections assuming C092100700004 spectra parametrization sigma/epsilon = A*exp(U/T) + C092100700005 B*U**n, where U is nuclear temperature. C092100700006 2(41-NB-93(P,3N)42-MO-91,,SIG,,MSC,DERIV) C092100700007 Calculated equilibrium cross sections assuming C092100700008 spectra parametrization sigma/epsilon = A*exp(U/T) + C092100700009 B*U**n, where U is nuclear temperature. C092100700010 ANALYSIS The nuclear temperatures determined at lower energy C092100700011 were used in a constant-temperature level density form C092100700012 for rho(U) and the best-fit values of A and B were C092100700013 calculated for n=0-6. C092100700014 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties C092100700015 STATUS (TABLE) Table IV, page 616 of J,PR/C,4,607,1971. C092100700016 HISTORY (20220629C) BP C092100700017 ENDBIB 15 0 C092100700018 NOCOMMON 0 0 C092100700019 DATA 5 4 C092100700020 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 C092100700021 MEV MB MB MB MB C092100700022 8.7 760.0 150.0 C092100700023 10.0 800.0 200.0 1100.0 350.0 C092100700024 12.3 75.0 25.0 1000.0 350.0 C092100700025 14.0 16.0 5.0 1700.0 800.0 C092100700026 ENDDATA 6 0 C092100700027 ENDSUBENT 26 0 C092100799999 SUBENT C0921008 20220805 20231011 C092100800001 BIB 5 15 C092100800002 REACTION 1(41-NB-93(P,N)42-MO-93,,SIG,,MSC,DERIV) C092100800003 Calculated equilibrium cross sections assuming C092100800004 spectra parametrization sigma/epsilon = A*exp(U/T) + C092100800005 B*U**n, where U is nuclear temperature. C092100800006 2(41-NB-93(P,3N)42-MO-91,,SIG,,MSC,DERIV) C092100800007 Calculated equilibrium cross sections assuming C092100800008 spectra parametrization sigma/epsilon = A*exp(U/T) + C092100800009 B*U**n, where U is nuclear temperature. C092100800010 ANALYSIS The nuclear temperatures determined at lower energy C092100800011 were used in a constant-temperature level density form C092100800012 for rho(U) and the best-fit values of A and B were C092100800013 calculated for n=0-6. C092100800014 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties C092100800015 STATUS (TABLE) Table IV, page 616 of J,PR/C,4,607,1971. C092100800016 HISTORY (20220629C) BP C092100800017 ENDBIB 15 0 C092100800018 NOCOMMON 0 0 C092100800019 DATA 5 3 C092100800020 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 C092100800021 MEV MB MB MB MB C092100800022 10.0 66.0 15.0 70.0 30.0 C092100800023 12.3 75.0 25.0 200.0 80.0 C092100800024 14.0 36.0 15.0 170.0 80.0 C092100800025 ENDDATA 5 0 C092100800026 ENDSUBENT 25 0 C092100899999 SUBENT C0921009 20220805 20231011 C092100900001 BIB 5 15 C092100900002 REACTION 1(73-TA-181(P,N)74-W-181,,SIG,,MSC,DERIV) C092100900003 Calculated equilibrium cross sections assuming C092100900004 spectra parametrization sigma/epsilon = A*exp(U/T) + C092100900005 B*U**n, where U is nuclear temperature. C092100900006 2(73-TA-181(P,3N)74-W-179,,SIG,,MSC,DERIV) C092100900007 Calculated equilibrium cross sections assuming C092100900008 spectra parametrization sigma/epsilon = A*exp(U/T) + C092100900009 B*U**n, where U is nuclear temperature. C092100900010 ANALYSIS The nuclear temperatures determined at lower energy C092100900011 were used in a constant-temperature level density form C092100900012 for rho(U) and the best-fit values of A and B were C092100900013 calculated for n=0-6. C092100900014 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties C092100900015 STATUS (TABLE) Table IV, page 616 of J,PR/C,4,607,1971. C092100900016 HISTORY (20220629C) BP C092100900017 ENDBIB 15 0 C092100900018 NOCOMMON 0 0 C092100900019 DATA 5 5 C092100900020 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 C092100900021 MEV MB MB MB MB C092100900022 8.7 77.0 20.0 110.0 30.0 C092100900023 10.0 36.0 10.0 330.0 140.0 C092100900024 10.4 30.0 10.0 580.0 300.0 C092100900025 11.7 6.0 2.0 900.0 400.0 C092100900026 12.3 2.0 1.0 800.0 400.0 C092100900027 ENDDATA 7 0 C092100900028 ENDSUBENT 27 0 C092100999999 SUBENT C0921010 20220805 20231011 C092101000001 BIB 5 15 C092101000002 REACTION 1(73-TA-181(P,N)74-W-181,,SIG,,MSC,DERIV) C092101000003 Calculated equilibrium cross sections assuming C092101000004 spectra parametrization sigma/epsilon = A*exp(U/T) + C092101000005 B*U**n, where U is nuclear temperature. C092101000006 2(73-TA-181(P,3N)74-W-179,,SIG,,MSC,DERIV) C092101000007 Calculated equilibrium cross sections assuming C092101000008 spectra parametrization sigma/epsilon = A*exp(U/T) + C092101000009 B*U**n, where U is nuclear temperature. C092101000010 ANALYSIS The nuclear temperatures determined at lower energy C092101000011 were used in a constant-temperature level density form C092101000012 for rho(U) and the best-fit values of A and B were C092101000013 calculated for n=0-6. C092101000014 ERR-ANALYS (DATA-ERR) No information on sources of uncertainties C092101000015 STATUS (TABLE) Table IV, page 616 of J,PR/C,4,607,1971. C092101000016 HISTORY (20220629C) BP C092101000017 ENDBIB 15 0 C092101000018 NOCOMMON 0 0 C092101000019 DATA 5 5 C092101000020 EN DATA 1DATA-ERR 1DATA 2DATA-ERR 2 C092101000021 MEV MB MB MB MB C092101000022 10.0 6.0 3.0 9.0 5.0 C092101000023 10.4 9.0 5.0 15.0 10.0 C092101000024 11.7 15.0 5.0 37.0 15.0 C092101000025 12.3 15.0 5.0 43.0 15.0 C092101000026 14.8 20.0 8.0 70.0 30.0 C092101000027 ENDDATA 7 0 C092101000028 ENDSUBENT 27 0 C092101099999 ENDENTRY 10 0 C092199999999