ENTRY 23049 20110206 22262304900000001 SUBENT 23049001 20110206 22262304900100001 BIB 12 63 2304900100002 REFERENCE (J,YF,71,(11),1910,2008) 2304900100003 (J,PAN,71,(11),1880,2008) Engl.transl. of YF,71,1910. 2304900100004 #doi:10.1134/S1063778808110057 2304900100005 (S,ISINN-15,8,2008) 2304900100006 (W,Bondarenko,20090127) 2304900100007 AUTHOR (S.S.Arzumanov,L.N.Bondarenko,P.Geltenbort,V.I.Morozov,2304900100008 Yu.N.Panin, S.M.Chernyavskiy) 2304900100009 TITLE Measurement of cross sections for inelastic 2304900100010 cold-neutron scattering in metals and polymers by 2304900100011 method of (n,gamma) analysis. 2304900100012 INSTITUTE (2FR ILL) P.Geltenbort . 2304900100013 (4RUSKUR) S.S.Arzumanov,L.N.Bondarenko,V.I.Morozov, 2304900100014 Yu.N.Panin, S.M.Chernyavskiy . 2304900100015 FACILITY (REAC,2FR ILL) ILL High Flux reactor . 2304900100016 INC-SOURCE (REAC) Ultra cold neutrons of energy 50-200 neV come 2304900100017 from TGV source of the ILL High Flux reactor to the 2304900100018 spectrum shaper, which wall is coated by Fomblin oil 2304900100019 with limited energy 106 neV. Leaving the shaper with 2304900100020 energy 50-106 neV and accelerating in vertical neutron2304900100021 guide 150 or 200 cm long and made of Ni, neutrons of 2304900100022 energy 200-255 or 250-305 neV hit the plane sample of 2304900100023 total absorption placed in the chamber. 2304900100024 DETECTOR (HE3SP) He-3 filled neutron detector to control the 2304900100025 neutron flux and its absorption. 2304900100026 (HPGE) Ge(HP)- gamma-ray detector of energy resolution 2304900100027 2.5 keV for 661-keV gamma-rays. At 15 cm distance from2304900100028 sample center. 2304900100029 METHOD The capture event is accompanied by prompt 2304900100030 characteristic gamma-rays with the known energies, that2304900100031 correspond to isotopes composed the sample. 2304900100032 The up-scattering event transfers VCN into thermal 2304900100033 neutron that flies away the sample and then being 2304900100034 captured by B-10-converter generates gamma-ray of 2304900100035 477 keV at reaction B-10(N,A+G)Li-7 . 2304900100036 SET-up calibration was made with Al-sample 2mm thick, 2304900100037 fluorine substituted oil by using 477 keV gamma-peak of2304900100038 B-10(N,A+G)Li-7 ; 2304900100039 polyethylene by using 2223 keV gamma-peak of (npdgamma)2304900100040 reaction. 2304900100041 ANALYSIS Neutron inelastic scattering cross section is deduced 2304900100042 from the ratio of registered counts of capture and 2304900100043 up-scattering events using the known capture cross 2304900100044 section for basic isotopes of the sample. 2304900100045 SAMPLE Solid samples as disks of 7 cm diameter, mounted into 2304900100046 a cooled copper ring onto a stainless steel foil of 2304900100047 100 microm thick, to which a converter as disk from 2304900100048 boron-containing rubber of 10 mm thick was pressed. 2304900100049 The sample temperature was preset between 300 and 2304900100050 100 K by varying the rate of liquid-nitrogen injection2304900100051 into the cooling spiral of copper ring. 2304900100052 Liquid sample: liquid was poured directly onto the 2304900100053 foil pressed tightly to the copper-ring plane 2304900100054 with boron-containing rubber. 2304900100055 The thickness of samples was chosen to ensure a 2304900100056 complete absorption of the incident neutron flux in 2304900100057 sample. 2304900100058 STATUS (TABLE) 29.01.2008 from L.N.Bondarenko. 2304900100059 (APRVD) 2304900100060 HISTORY (20081222C) M.M. 2304900100061 (20110206U) SD: DOI identifier was corrected. 2304900100062 DECAY-DATA deleted. This value is not given in the 2304900100063 ref. and the reaction 10B(n,alpha)7Li-L1 is used as 2304900100064 a converter to produce 477 keV gamma-rays 2304900100065 ENDBIB 63 0 2304900100066 COMMON 1 3 2304900100067 EN 2304900100068 EV 2304900100069 0.0253 2304900100070 ENDCOMMON 3 0 2304900100071 ENDSUBENT 70 0 2304900199999 SUBENT 23049002 20081222 22072304900200001 BIB 3 5 2304900200002 REACTION (4-BE-9(N,THS)4-BE-9,,SIG) 2304900200003 ERR-ANALYS (DATA-ERR) Not specified. 2304900200004 STATUS (TABLE) 30.01.2008 from L.N.Bondarenko. 2304900200005 Data are presented on Fig.5 of 1-st reference, 2304900200006 Fig.3 of 2-nd reference. 2304900200007 ENDBIB 5 0 2304900200008 NOCOMMON 0 0 2304900200009 DATA 4 10 2304900200010 TEMP TEMP-ERR DATA DATA-ERR 2304900200011 K K B B 2304900200012 93. 5. 0.0038 0.0007 2304900200013 113. 5. 0.008 0.001 2304900200014 138. 5. 0.0142 0.0016 2304900200015 173. 5. 0.0309 0.0029 2304900200016 193. 5. 0.0545 0.0053 2304900200017 216. 5. 0.0553 0.0045 2304900200018 238. 5. 0.0716 0.006 2304900200019 261. 5. 0.0808 0.0071 2304900200020 283. 5. 0.1028 0.0096 2304900200021 296. 3. 0.117 0.0051 2304900200022 ENDDATA 12 0 2304900200023 ENDSUBENT 22 0 2304900299999 SUBENT 23049003 20081222 22072304900300001 BIB 3 5 2304900300002 REACTION (13-AL-27(N,THS)13-AL-27,,SIG) 2304900300003 ERR-ANALYS (DATA-ERR) Not specified. 2304900300004 STATUS (TABLE) 30.01.2008 from L.N.Bondarenko. 2304900300005 Data are presented on Fig.5 of 1-st reference, 2304900300006 Fig.3 of 2-nd reference. 2304900300007 ENDBIB 5 0 2304900300008 NOCOMMON 0 0 2304900300009 DATA 4 6 2304900300010 TEMP TEMP-ERR DATA DATA-ERR 2304900300011 K K B B 2304900300012 108. 5. 0.0004 0.0032 2304900300013 150. 5. 0.0099 0.0028 2304900300014 193. 5. 0.0258 0.0027 2304900300015 230. 5. 0.026 0.003 2304900300016 270. 5. 0.0406 0.0039 2304900300017 298. 3. 0.0454 0.0026 2304900300018 ENDDATA 8 0 2304900300019 ENDSUBENT 18 0 2304900399999 SUBENT 23049004 20081222 22072304900400001 BIB 4 12 2304900400002 REACTION (28-NI-0(N,THS)28-NI-0,,SIG) 2304900400003 ERR-ANALYS (DATA-ERR) Not specified. 2304900400004 ANALYSIS Data of the nickel isotopic composition and the 2304900400005 capture cross sections of these isotopes in thermal 2304900400006 region were taken into account.Measured counting rates2304900400007 for gamma rays emitted in the main transitions 2304900400008 following neutron capture on Ni-58 isotope and the 2304900400009 corresponding gamma-ray yields per neutron capture 2304900400010 event were used to determine inelastic cross section. 2304900400011 STATUS (TABLE) 30.01.2008 from L.N.Bondarenko. 2304900400012 Data are presented on Fig.5 of 1-st reference, 2304900400013 Fig.3 of 2-nd reference. 2304900400014 ENDBIB 12 0 2304900400015 NOCOMMON 0 0 2304900400016 DATA 4 8 2304900400017 TEMP TEMP-ERR DATA DATA-ERR 2304900400018 K K B B 2304900400019 86. 5. 0.101197 0.023387 2304900400020 93. 5. 0.078626 0.030233 2304900400021 138. 5. 0.176030 0.033477 2304900400022 176. 5. 0.168478 0.029033 2304900400023 208. 5. 0.213787 0.030652 2304900400024 238. 5. 0.199243 0.029762 2304900400025 268. 5. 0.169039 0.032629 2304900400026 296. 3. 0.270009 0.034666 2304900400027 ENDDATA 10 0 2304900400028 ENDSUBENT 27 0 2304900499999 SUBENT 23049005 20081222 22072304900500001 BIB 4 6 2304900500002 REACTION (6-C-0(N,THS)6-C-0,,SIG) 2304900500003 SAMPLE Reactor graphite. 2304900500004 ERR-ANALYS (DATA-ERR) Not specified. 2304900500005 STATUS (TABLE) 30.01.2008 from L.N.Bondarenko. 2304900500006 Data are presented on Fig.5 of 1-st reference, 2304900500007 Fig.3 of 2-nd reference. 2304900500008 ENDBIB 6 0 2304900500009 NOCOMMON 0 0 2304900500010 DATA 4 6 2304900500011 TEMP TEMP-ERR DATA DATA-ERR 2304900500012 K K B B 2304900500013 98. 5. 0.012840 0.00289 2304900500014 138. 5. 0.040986 0.00519 2304900500015 193. 5. 0.080187 0.01046 2304900500016 238. 5. 0.083758 0.00978 2304900500017 273. 5. 0.101105 0.01811 2304900500018 296. 3. 0.128231 0.00901 2304900500019 ENDDATA 8 0 2304900500020 ENDSUBENT 19 0 2304900599999 SUBENT 23049006 20081222 22072304900600001 BIB 4 6 2304900600002 REACTION (1-H-PLE(N,THS)1-H-PLE,,SIG) 2304900600003 SAMPLE Polyethylene. 2304900600004 ERR-ANALYS (DATA-ERR) Not specified. 2304900600005 STATUS (TABLE) 29.01.2008 from L.N.Bondarenko. 2304900600006 Data are presented on Fig.5 of 1-st reference, 2304900600007 Fig.3 of 2-nd reference. 2304900600008 ENDBIB 6 0 2304900600009 NOCOMMON 0 0 2304900600010 DATA 4 24 2304900600011 TEMP TEMP-ERR DATA DATA-ERR 2304900600012 K K B B 2304900600013 108. 5. 1.0213 0.0363 2304900600014 118. 5. 1.1765 0.0650 2304900600015 128. 5. 1.5577 0.0651 2304900600016 128. 5. 1.5282 0.1221 2304900600017 138. 5. 1.4582 0.0788 2304900600018 153. 5. 1.6114 0.0725 2304900600019 163. 5. 1.7958 0.0988 2304900600020 175. 5. 2.1752 0.1048 2304900600021 192. 5. 2.3991 0.0923 2304900600022 213. 5. 2.5734 0.1467 2304900600023 223. 5. 2.7842 0.1400 2304900600024 237. 5. 2.8026 0.1486 2304900600025 253. 5. 2.9917 0.1757 2304900600026 263. 5. 3.1125 0.1762 2304900600027 273. 5. 3.0133 0.1790 2304900600028 281. 5. 3.5296 0.2284 2304900600029 285. 5. 3.8457 0.2374 2304900600030 290. 5. 3.3688 0.1929 2304900600031 290. 5. 3.5179 0.1948 2304900600032 296. 3. 3.4418 0.1396 2304900600033 296. 5. 3.6186 0.1630 2304900600034 308. 5. 3.6275 0.1885 2304900600035 321. 5. 3.9805 0.2355 2304900600036 328. 5. 3.8408 0.3968 2304900600037 ENDDATA 26 0 2304900600038 ENDSUBENT 37 0 2304900699999 SUBENT 23049007 20081222 22072304900700001 BIB 4 6 2304900700002 REACTION (9-F-CMP(N,THS)9-F-CMP,,SIG) 2304900700003 SAMPLE Teflon. 2304900700004 ERR-ANALYS (DATA-ERR) Not specified. 2304900700005 STATUS (TABLE) 30.01.2008 from L.N.Bondarenko. 2304900700006 Data are presented on Fig.5 of 1-st reference, 2304900700007 Fig.3 of 2-nd reference. 2304900700008 ENDBIB 6 0 2304900700009 NOCOMMON 0 0 2304900700010 DATA 4 8 2304900700011 TEMP TEMP-ERR DATA DATA-ERR 2304900700012 K K B B 2304900700013 103. 5. 0.1242 0.0103 2304900700014 136. 5. 0.1597 0.0133 2304900700015 156. 5. 0.1877 0.0158 2304900700016 186. 5. 0.1656 0.0154 2304900700017 213. 5. 0.2115 0.0193 2304900700018 243. 5. 0.2011 0.0198 2304900700019 273. 5. 0.2315 0.023 2304900700020 296. 3. 0.2566 0.0111 2304900700021 ENDDATA 10 0 2304900700022 ENDSUBENT 21 0 2304900799999 SUBENT 23049008 20081222 22072304900800001 BIB 4 6 2304900800002 REACTION (9-F-CMP(N,THS)9-F-CMP,,SIG) 2304900800003 SAMPLE Fluoropolymer YL VAC18/8 : (F3CCF2OCF2CF5)16 2304900800004 ERR-ANALYS (DATA-ERR) Not specified. 2304900800005 STATUS (TABLE) 30.01.2008 from L.N.Bondarenko. 2304900800006 Data are presented on Fig.5 of 1-st reference, 2304900800007 Fig.3 of 2-nd reference. 2304900800008 ENDBIB 6 0 2304900800009 NOCOMMON 0 0 2304900800010 DATA 4 8 2304900800011 TEMP TEMP-ERR DATA DATA-ERR 2304900800012 K K B B 2304900800013 113. 5. 0.086877 0.003598 2304900800014 133. 5. 0.085043 0.007160 2304900800015 156. 5. 0.093931 0.005291 2304900800016 190. 5. 0.090616 0.005009 2304900800017 228. 5. 0.113825 0.006913 2304900800018 253. 5. 0.122432 0.007972 2304900800019 268. 5. 0.129592 0.007089 2304900800020 296. 3. 0.159997 0.004021 2304900800021 ENDDATA 10 0 2304900800022 ENDSUBENT 21 0 2304900899999 SUBENT 23049009 20081222 22072304900900001 BIB 4 6 2304900900002 REACTION (9-F-CMP(N,THS)9-F-CMP,,SIG) 2304900900003 SAMPLE Fluoropolymer PEV-130 : (OCFCF3CF2)16 . 2304900900004 ERR-ANALYS (DATA-ERR) Not specified. 2304900900005 STATUS (TABLE) 30.01.2008 from L.N.Bondarenko. 2304900900006 Data are presented on Fig.5 of 1-st reference, 2304900900007 Fig.3 of 2-nd reference. 2304900900008 ENDBIB 6 0 2304900900009 NOCOMMON 0 0 2304900900010 DATA 4 5 2304900900011 TEMP TEMP-ERR DATA DATA-ERR 2304900900012 K K B B 2304900900013 175. 5. 0.083526 0.004268 2304900900014 193. 5. 0.097776 0.006667 2304900900015 223. 5. 0.127617 0.008924 2304900900016 253. 5. 0.136223 0.008465 2304900900017 296. 3. 0.176364 0.011040 2304900900018 ENDDATA 7 0 2304900900019 ENDSUBENT 18 0 2304900999999 SUBENT 23049010 20081222 22072304901000001 BIB 4 6 2304901000002 REACTION (9-F-CMP(N,THS)9-F-CMP,,SIG) 2304901000003 SAMPLE Fluoropolymer Fomblin : CF9(CF2O)16(CF2CF2O)CF3 . 2304901000004 ERR-ANALYS (DATA-ERR) Not specified. 2304901000005 STATUS (TABLE) 30.01.2008 from L.N.Bondarenko. 2304901000006 Data are presented on Fig.5 of 1-st reference, 2304901000007 Fig.3 of 2-nd reference. 2304901000008 ENDBIB 6 0 2304901000009 NOCOMMON 0 0 2304901000010 DATA 4 11 2304901000011 TEMP TEMP-ERR DATA DATA-ERR 2304901000012 K K B B 2304901000013 108. 5. 0.038056 0.004852 2304901000014 108. 5. 0.037449 0.004539 2304901000015 115. 5. 0.042292 0.005445 2304901000016 123. 5. 0.054577 0.005782 2304901000017 141. 5. 0.069281 0.006249 2304901000018 168. 5. 0.073668 0.006026 2304901000019 208. 5. 0.125538 0.010199 2304901000020 228. 5. 0.149234 0.012056 2304901000021 253. 5. 0.166648 0.014229 2304901000022 268. 5. 0.179049 0.014013 2304901000023 296. 3. 0.230051 0.018839 2304901000024 ENDDATA 13 0 2304901000025 ENDSUBENT 24 0 2304901099999 ENDENTRY 10 0 2304999999999