ENTRY 21185 20211227 23062118500000001 SUBENT 21185001 20211227 23062118500100001 BIB 12 38 2118500100002 TITLE Delayed neutron investigations with the ZEPHYR fast 2118500100003 reactor. Part II: The delayed neutrons arising from 2118500100004 fast fission in U-235, U-233, U-238, Pu-239 and 2118500100005 Th-232. 2118500100006 AUTHOR (H.Rose,R.D.Smith) 2118500100007 INSTITUTE (2UK HAR) 2118500100008 REFERENCE (J,JNE,4,141,1957) Main reference, part II of the 2118500100009 paper. Data are given 2118500100010 (J,JNE,4,133,1957) Part I of the paper. Experimental 2118500100011 details 2118500100012 FACILITY (REAC,2UK HAR) ZERHYR reactor at AERE. 2118500100013 INC-SOURCE (REAC) Natural uranium envelope of fast reactor. 2118500100014 INC-SPECT Fast spectrum with mean energy 1 MeV. Flux at sample 2118500100015 position estimated to be (1.39+-0.07)E+08 n/cm-sq/sec 2118500100016 METHOD (FISCT) Detection of emitted neutrons following 2118500100017 reactor irradiation. 2118500100018 DETECTOR (BF3) Group of six BF-3 counters, 1 inch diameter 2118500100019 and 12 inches long, embedded in a cylinder of 2118500100020 paraffin wax, 32 cm diameter and 41 cm long. 2118500100021 Sample transferred from reactor to detectors 2118500100022 using a pneumatic system described in part I 2118500100023 of the paper. 2118500100024 (FISCH) Fission rate measured in fission chamber 2118500100025 containing appropriate material and placed in 2118500100026 same position as the sample in pneumatic tube. 2118500100027 CORRECTION Correction for variation of detector efficiency with 2118500100028 neutron energy. 2118500100029 ERR-ANALYS (DATA-ERR) Errors are not specified 2118500100030 HISTORY (19791119C) 2118500100031 (19800709A) G.C., Reaction string in subwork 2118500100032 6 corrected. 2118500100033 (20071223A) Date is corrected - SM 2118500100034 (20071224U) SUBENT 006 corrected. Several new SUBENTS 2118500100035 added with data from main reference - SM 2118500100036 (20211227A) SD: Corrections in all Subents. 2118500100037 Subents 017-021 deleted (Ratio of the nu-d/nu-tot 2118500100038 derived from the measured nu-d and nu-tot derived from 2118500100039 thermal nu-tot assuming dnu-tot/dE=0.12 neutrons/MeV.).2118500100040 ENDBIB 38 0 2118500100041 COMMON 1 3 2118500100042 EN-MEAN 2118500100043 MEV 2118500100044 1. 2118500100045 ENDCOMMON 3 0 2118500100046 ENDSUBENT 45 0 2118500199999 SUBENT 21185002 20211227 23062118500200001 BIB 4 4 2118500200002 REACTION (92-U-235(N,F),,SIG,,SPA) 2118500200003 SAMPLE 5.75 gram of U-235. 2118500200004 STATUS (TABLE) Table 1 of J.Nucl.En.,4(1957)141 2118500200005 HISTORY (20211227U) SD: STATUS updated. 2118500200006 ENDBIB 4 0 2118500200007 NOCOMMON 0 0 2118500200008 DATA 2 1 2118500200009 DATA DATA-ERR 2118500200010 B B 2118500200011 1.59 7.E-02 2118500200012 ENDDATA 3 0 2118500200013 ENDSUBENT 12 0 2118500299999 SUBENT 21185003 20211227 23062118500300001 BIB 5 6 2118500300002 REACTION (92-U-0(N,F),,SIG,,SPA) 2118500300003 SAMPLE 72.5 gram of natural uranium. 2118500300004 CORRECTION Corrected for U-235 contribution (about 10% 2118500300005 of total delayed neutrons). 2118500300006 STATUS (TABLE) Table 1 of J.Nucl.En.,4(1957)141 2118500300007 HISTORY (20211227U) SD: STATUS updated. 2118500300008 ENDBIB 6 0 2118500300009 NOCOMMON 0 0 2118500300010 DATA 2 1 2118500300011 DATA DATA-ERR 2118500300012 B B 2118500300013 5.6E-02 3.E-03 2118500300014 ENDDATA 3 0 2118500300015 ENDSUBENT 14 0 2118500399999 SUBENT 21185004 20211227 23062118500400001 BIB 4 4 2118500400002 REACTION (92-U-233(N,F),,SIG,,SPA) 2118500400003 SAMPLE 10.0 gram of U-233. 2118500400004 STATUS (TABLE) Table 1 of J.Nucl.En.,4(1957)141 2118500400005 HISTORY (20211227U) SD: STATUS updated. 2118500400006 ENDBIB 4 0 2118500400007 NOCOMMON 0 0 2118500400008 DATA 2 1 2118500400009 DATA DATA-ERR 2118500400010 B B 2118500400011 2.43 1.2E-01 2118500400012 ENDDATA 3 0 2118500400013 ENDSUBENT 12 0 2118500499999 SUBENT 21185005 20211227 23062118500500001 BIB 4 4 2118500500002 REACTION (94-PU-239(N,F),,SIG,,SPA) 2118500500003 SAMPLE 9.74 gram of Pu-239. 2118500500004 STATUS (TABLE) Table 1 of J.Nucl.En.,4(1957)141 2118500500005 HISTORY (20211227U) SD: STATUS updated. 2118500500006 ENDBIB 4 0 2118500500007 NOCOMMON 0 0 2118500500008 DATA 2 1 2118500500009 DATA DATA-ERR 2118500500010 B B 2118500500011 1.79 4.E-02 2118500500012 ENDDATA 3 0 2118500500013 ENDSUBENT 12 0 2118500599999 SUBENT 21185006 20211227 23062118500600001 BIB 4 7 2118500600002 REACTION (90-TH-232(N,F),,SIG,,SPA) 2118500600003 SAMPLE 43.9 gram natural thorium. 2118500600004 STATUS (TABLE) Table 1 of J.Nucl.En.,4(1957)141 2118500600005 HISTORY (19800609A) G.C., Reaction string 3 corrected. 2118500600006 (20071224A) REACTION strings 2 - 4 moved to another 2118500600007 SUBENT 2118500600008 (20211227U) SD: STATUS updated. 2118500600009 ENDBIB 7 0 2118500600010 NOCOMMON 0 0 2118500600011 DATA 2 1 2118500600012 DATA DATA-ERR 2118500600013 B B 2118500600014 1.34E-02 3.E-03 2118500600015 ENDDATA 3 0 2118500600016 ENDSUBENT 15 0 2118500699999 SUBENT 21185007 20211227 23062118500700001 BIB 4 6 2118500700002 REACTION ((90-TH-232(N,F),DL/GRP,NU,,SPA)/ 2118500700003 (90-TH-232(N,F),DL,NU,,SPA)) 2118500700004 SAMPLE 43.9 gram natural thorium. 2118500700005 STATUS (TABLE) Table 2 of J.Nucl.En.,4(1957)141 2118500700006 HISTORY (20071224C) S.M. 2118500700007 (20211227U) SD: STATUS updated. 2118500700008 ENDBIB 6 0 2118500700009 NOCOMMON 0 0 2118500700010 DATA 3 5 2118500700011 HL DATA DATA-ERR 2118500700012 SEC NO-DIM NO-DIM 2118500700013 55.6 0.033 0.002 2118500700014 22.0 0.134 0.008 2118500700015 4.51 0.308 0.024 2118500700016 1.52 0.400 0.032 2118500700017 0.43 0.125 0.030 2118500700018 ENDDATA 7 0 2118500700019 ENDSUBENT 18 0 2118500799999 SUBENT 21185008 20211227 23062118500800001 BIB 4 6 2118500800002 REACTION ((92-U-235(N,F),DL/GRP,NU,,SPA)/ 2118500800003 (92-U-235(N,F),DL,NU,,SPA)) 2118500800004 SAMPLE 5.75 gram U-235 2118500800005 STATUS (TABLE) Table 2 of J.Nucl.En.,4(1957)141 2118500800006 HISTORY (20071224C) S.M. 2118500800007 (20211227U) SD: STATUS updated. 2118500800008 ENDBIB 6 0 2118500800009 NOCOMMON 0 0 2118500800010 DATA 3 5 2118500800011 HL DATA DATA-ERR 2118500800012 SEC NO-DIM NO-DIM 2118500800013 55.6 0.035 0.001 2118500800014 22.0 0.224 0.007 2118500800015 4.51 0.340 0.017 2118500800016 1.52 0.320 0.021 2118500800017 0.43 0.081 0.027 2118500800018 ENDDATA 7 0 2118500800019 ENDSUBENT 18 0 2118500899999 SUBENT 21185009 20211227 23062118500900001 BIB 4 6 2118500900002 REACTION ((92-U-233(N,F),DL/GRP,NU,,SPA)/ 2118500900003 (92-U-233(N,F),DL,NU,,SPA)) 2118500900004 SAMPLE 10.0 gram of U-233 2118500900005 STATUS (TABLE) Table 2 of J.Nucl.En.,4(1957)141 2118500900006 HISTORY (20071224C) S.M. 2118500900007 (20211227U) SD: STATUS updated. 2118500900008 ENDBIB 6 0 2118500900009 NOCOMMON 0 0 2118500900010 DATA 3 5 2118500900011 HL DATA DATA-ERR 2118500900012 SEC NO-DIM NO-DIM 2118500900013 55.6 0.080 0.003 2118500900014 22.0 0.283 0.023 2118500900015 4.51 0.383 0.023 2118500900016 1.52 0.221 0.022 2118500900017 0.43 0.033 0.015 2118500900018 ENDDATA 7 0 2118500900019 ENDSUBENT 18 0 2118500999999 SUBENT 21185010 20211227 23062118501000001 BIB 5 8 2118501000002 REACTION ((92-U-238(N,F),DL/GRP,NU,,SPA)/ 2118501000003 (92-U-238(N,F),DL,NU,,SPA)) 2118501000004 ANALYSIS A contribution of U-236 fission about 10% was 2118501000005 subtracted from the measured value for U-238 2118501000006 SAMPLE 72.5 gram of U-nat 2118501000007 STATUS (TABLE) Table 2 of J.Nucl.En.,4(1957)141 2118501000008 HISTORY (20071224C) S.M. 2118501000009 (20211227U) SD: STATUS updated. 2118501000010 ENDBIB 8 0 2118501000011 NOCOMMON 0 0 2118501000012 DATA 3 5 2118501000013 HL DATA DATA-ERR 2118501000014 SEC NO-DIM NO-DIM 2118501000015 55.6 0.012 0.001 2118501000016 22.0 0.154 0.005 2118501000017 4.51 0.266 0.017 2118501000018 1.52 0.401 0.032 2118501000019 0.43 0.167 0.033 2118501000020 ENDDATA 7 0 2118501000021 ENDSUBENT 20 0 2118501099999 SUBENT 21185011 20211227 23062118501100001 BIB 4 6 2118501100002 REACTION ((94-PU-239(N,F),DL/GRP,NU,,SPA)/ 2118501100003 (94-PU-239(N,F),DL,NU,,SPA)) 2118501100004 SAMPLE 9.74 gram of Pu-239 2118501100005 STATUS (TABLE) Table 2 of J.Nucl.En.,4(1957)141 2118501100006 HISTORY (20071224C) S.M. 2118501100007 (20211227U) SD: STATUS updated. 2118501100008 ENDBIB 6 0 2118501100009 NOCOMMON 0 0 2118501100010 DATA 3 5 2118501100011 HL DATA DATA-ERR 2118501100012 SEC NO-DIM NO-DIM 2118501100013 55.6 0.031 0.002 2118501100014 22.0 0.304 0.013 2118501100015 4.51 0.317 0.014 2118501100016 1.52 0.293 0.024 2118501100017 0.43 0.055 0.018 2118501100018 ENDDATA 7 0 2118501100019 ENDSUBENT 18 0 2118501199999 SUBENT 21185012 20211227 23062118501200001 BIB 4 8 2118501200002 REACTION 1((90-TH-232(N,F),DL,NU,,SPA)/ 2118501200003 (92-U-235(N,F),,NU,,SPA)) 2118501200004 2(90-TH-232(N,F),DL,NU,,SPA) 2118501200005 SAMPLE 43.9 gram of natural thorium. 2118501200006 STATUS (TABLE) Table 2 of J.Nucl.En.,4(1957)141 2118501200007 HISTORY (20071224C) S.M. 2118501200008 (20211227A) SD: REACTION code (1) changed. 2118501200009 STATUS updated. 2118501200010 ENDBIB 8 0 2118501200011 NOCOMMON 0 0 2118501200012 DATA 4 1 2118501200013 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2118501200014 NO-DIM NO-DIM PC/FIS PC/FIS 2118501200015 2.21 2.7E-01 3.8 8.E-01 2118501200016 ENDDATA 3 0 2118501200017 ENDSUBENT 16 0 2118501299999 SUBENT 21185013 20211223 23062118501300001 BIB 4 7 2118501300002 REACTION (92-U-235(N,F),DL,NU,,SPA) 2118501300003 SAMPLE 5.75 g U-235 2118501300004 STATUS (TABLE) Table 3 of J.Nucl.Energ.,4(1957)141 2118501300005 HISTORY (20071224C) S.M. 2118501300006 (20211227A) SD: REACTION (1) deleted (The authors give 2118501300007 the ratio 235U(n,f),,NU)/235U(n,f),,NU), which is 1 2118501300008 as should be. 2118501300009 ENDBIB 7 0 2118501300010 NOCOMMON 0 0 2118501300011 DATA 2 1 2118501300012 DATA DATA-ERR 2118501300013 PC/FIS PC/FIS 2118501300014 1.74 0.14 2118501300015 ENDDATA 3 0 2118501300016 ENDSUBENT 15 0 2118501399999 SUBENT 21185014 20211227 23062118501400001 BIB 4 8 2118501400002 REACTION 1((92-U-233(N,F),DL,NU,,SPA)/ 2118501400003 (92-U-235(N,F),,NU,,SPA)) 2118501400004 2(92-U-233(N,F),DL,NU,,SPA) 2118501400005 SAMPLE 10.0 gram of U-233 2118501400006 STATUS (TABLE) Table 3 of J.Nucl.En.,4(1957)141 2118501400007 HISTORY (20071224C) S.M. 2118501400008 (20211227A) SD: REACTION code (1) changed. 2118501400009 STATUS updated. 2118501400010 ENDBIB 8 0 2118501400011 NOCOMMON 0 0 2118501400012 DATA 4 1 2118501400013 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2118501400014 NO-DIM NO-DIM PC/FIS PC/FIS 2118501400015 0.429 0.026 0.74 0.06 2118501400016 ENDDATA 3 0 2118501400017 ENDSUBENT 16 0 2118501499999 SUBENT 21185015 20211227 23062118501500001 BIB 4 8 2118501500002 REACTION 1((92-U-238(N,F),DL,NU,,SPA)/ 2118501500003 (92-U-235(N,F),,NU,,SPA)) 2118501500004 2(92-U-238(N,F),DL,NU,,SPA) 2118501500005 SAMPLE 72.5 gram of U-nat 2118501500006 STATUS (TABLE) Table 3 of J.Nucl.En.,4(1957)141 2118501500007 HISTORY (20071224C) S.M. 2118501500008 (20211227A) SD: REACTION code (1) changed. 2118501500009 STATUS updated. 2118501500010 ENDBIB 8 0 2118501500011 NOCOMMON 0 0 2118501500012 DATA 4 1 2118501500013 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2118501500014 NO-DIM NO-DIM PC/FIS PC/FIS 2118501500015 2.20 0.15 3.7 0.4 2118501500016 ENDDATA 3 0 2118501500017 ENDSUBENT 16 0 2118501599999 SUBENT 21185016 20211227 23062118501600001 BIB 4 8 2118501600002 REACTION 1((94-PU-239(N,F),DL,NU,,SPA)/ 2118501600003 (92-U-235(N,F),,NU,,SPA)) 2118501600004 2(94-PU-239(N,F),DL,NU,,SPA) 2118501600005 SAMPLE 9.74 gram PU-239 2118501600006 STATUS (TABLE) Table 3 of J.Nucl.En.,4(1957)141 2118501600007 HISTORY (20071224C) S.M. 2118501600008 (20211227A) SD: REACTION code (1) changed. 2118501600009 STATUS updated. 2118501600010 ENDBIB 8 0 2118501600011 NOCOMMON 0 0 2118501600012 DATA 4 1 2118501600013 DATA 1DATA-ERR 1DATA 2DATA-ERR 2 2118501600014 NO-DIM NO-DIM PC/FIS PC/FIS 2118501600015 0.406 0.024 0.70 0.06 2118501600016 ENDDATA 3 0 2118501600017 ENDSUBENT 16 0 2118501699999 NOSUBENT 21185017 20211227 23062118501700001 NOSUBENT 21185018 20211227 23062118501800001 NOSUBENT 21185019 20211227 23062118501900001 NOSUBENT 21185020 20211227 23062118502000001 NOSUBENT 21185021 20211227 23062118502100001 ENDENTRY 21 0 2118599999999