ENTRY 30320 20100204 31443032000000001 SUBENT 30320001 20100204 31443032000100001 BIB 11 33 3032000100002 TITLE Emission of light nuclei in thermal neutron fission 3032000100003 of Pu-239. 3032000100004 AUTHOR (T.Krogulski, J.Chwaszczewska, M.Dakowski, E.Piasecki, 3032000100005 M.Sowinski) 3032000100006 INSTITUTE (3POLIFJ) 3032000100007 REFERENCE (J,NP/A,128,219,196904) 3032000100008 (R,INR-1142,196911) in Polish, full paper, exp. detail 3032000100009 (C,69VIENNA,893,196906) Short note 3032000100010 FACILITY (REAC,3POLIPJ) EWA reactor at the IPJ 3032000100011 INC-SOURCE (REAC) EWA reactor. The original neutron spectrum is 3032000100012 relatively rich in fast neutron. Full pile spectrum 3032000100013 and epicadmium neutrons were used for measurement of 3032000100014 the hydrogen isotopes, for correction of background 3032000100015 due to (n,p) process induced by fast neutrons. 3032000100016 For He isotopes, only full reactor neutron spectrum 3032000100017 was used. 3032000100018 SAMPLE About 6 mg/cm2 thick Pu-239 target deposited on 3032000100019 tantalum foil of 13.25mg/cm2. 3032000100020 METHOD (EDE) Counter telescope with semiconductor detectors 3032000100021 DETECTOR (TELES,SOLST,SOLST) Semiconductor telescope. 3032000100022 The delta-E- and E- detectors are 50 mu and 1500 mu 3032000100023 thick, respectively. For the detection of helium 3032000100024 isotopes, a thinner delta- E-semiconductor detector 3032000100025 (25 mu) was used. 3032000100026 PART-DET (FF) H-1,H-2,H-3,He-4,He-6 and He-8. 3032000100027 HISTORY (19760115C) KO. 3032000100028 (20090115A) SD: BIB section updated. Subents 002,003 3032000100029 were restored. Reaction code was 3032000100030 corrected. Subent 004 was splited in 3032000100031 two: 004+005 3032000100032 (20100204A) On. METHOD: EDE added 3032000100033 REACTION code in Subent 005 was changed 3032000100034 according to EXFOR rules. 3032000100035 ENDBIB 33 0 3032000100036 COMMON 1 3 3032000100037 EN-DUMMY 3032000100038 EV 3032000100039 0.0253 3032000100040 ENDCOMMON 3 0 3032000100041 ENDSUBENT 40 0 3032000199999 SUBENT 30320002 20100204 31443032000200001 BIB 6 22 3032000200002 REACTION (94-PU-239(N,F)ELEM/MASS,TER,FY/DE,,REL) 3032000200003 Energy spectra of H-isotopes in ternary fission. 3032000200004 ANALYSIS Analysis the spectra of fast pile neutron and 3032000200005 fission neutrons from the sample are expected to be 3032000200006 similar, and the spectra of protons from (np) 3032000200007 reactions induced by pile and fission neutrons are 3032000200008 also to be similar. So in the final result for 3032000200009 proton, the background was multiplied by a constant 3032000200010 factor before subtracting. this factor, 2.0 +-.0.2, 3032000200011 was defined as the ratio of the background due to 3032000200012 all neutrons to the background due to epicadmium 3032000200013 neutrons from the pile. All the spectra are 3032000200014 sufficiently well fitted by a Gaussian distribution. 3032000200015 ERR-ANALYS No error given 3032000200016 COMMENT The FWHM of the energy spectra are, (in MeV) 3032000200017 p 7.2 +- 0.3 3032000200018 d 7.2 +- 0.5 3032000200019 t 7.6 +- 0.4 3032000200020 STATUS (TABLE) Data from Piasecki as priv.comm.,25/11/75, 3032000200021 corresponding to fig.1 of J,NP/A,128,219,1969 3032000200022 HISTORY (20090115S) SD 3032000200023 (20100204A) On. SF6: DE -> FY/DE, SF8: Add REL 3032000200024 ENDBIB 22 0 3032000200025 COMMON 1 3 3032000200026 ELEMENT 3032000200027 NO-DIM 3032000200028 1. 3032000200029 ENDCOMMON 3 0 3032000200030 DATA 3 153 3032000200031 MASS E DATA 3032000200032 NO-DIM MEV ARB-UNITS 3032000200033 1. 4.25 241. 3032000200034 1. 4.5 224. 3032000200035 1. 4.75 290. 3032000200036 1. 5. 299. 3032000200037 1. 5.25 356. 3032000200038 1. 5.5 370. 3032000200039 1. 5.75 402. 3032000200040 1. 6. 416. 3032000200041 1. 6.25 436. 3032000200042 1. 6.5 459. 3032000200043 1. 6.75 482. 3032000200044 1. 7. 514. 3032000200045 1. 7.25 531. 3032000200046 1. 7.5 531. 3032000200047 1. 7.75 534. 3032000200048 1. 8. 591. 3032000200049 1. 8.25 594. 3032000200050 1. 8.5 611. 3032000200051 1. 8.75 611. 3032000200052 1. 9. 611. 3032000200053 1. 9.25 594. 3032000200054 1. 9.5 571. 3032000200055 1. 9.75 554. 3032000200056 1. 10. 531. 3032000200057 1. 10.25 508. 3032000200058 1. 10.5 500. 3032000200059 1. 10.75 485. 3032000200060 1. 11. 477. 3032000200061 1. 11.25 388. 3032000200062 1. 11.5 379. 3032000200063 1. 11.75 333. 3032000200064 1. 12. 333. 3032000200065 1. 12.25 307. 3032000200066 1. 12.5 290. 3032000200067 1. 12.75 235. 3032000200068 1. 13. 218. 3032000200069 1. 13.25 187. 3032000200070 1. 13.5 172. 3032000200071 1. 13.75 146. 3032000200072 1. 14. 129. 3032000200073 1. 14.25 115. 3032000200074 1. 14.5 98. 3032000200075 1. 14.75 89. 3032000200076 1. 15. 75. 3032000200077 1. 15.25 75. 3032000200078 1. 15.5 49. 3032000200079 1. 15.75 43. 3032000200080 1. 16. 26. 3032000200081 1. 16.25 26. 3032000200082 1. 16.5 9. 3032000200083 1. 16.75 9. 3032000200084 2. 5. 103. 3032000200085 2. 5.25 97. 3032000200086 2. 5.5 116. 3032000200087 2. 5.75 130. 3032000200088 2. 6. 135. 3032000200089 2. 6.25 140. 3032000200090 2. 6.5 160. 3032000200091 2. 6.75 176. 3032000200092 2. 7. 167. 3032000200093 2. 7.25 166. 3032000200094 2. 7.5 164. 3032000200095 2. 7.75 173. 3032000200096 2. 8. 178. 3032000200097 2. 8.25 185. 3032000200098 2. 8.5 190. 3032000200099 2. 8.75 185. 3032000200100 2. 9. 185. 3032000200101 2. 9.25 182. 3032000200102 2. 9.5 169. 3032000200103 2. 9.75 164. 3032000200104 2. 10. 167. 3032000200105 2. 10.25 164. 3032000200106 2. 10.5 145. 3032000200107 2. 10.75 131. 3032000200108 2. 11. 120. 3032000200109 2. 11.25 113. 3032000200110 2. 11.5 108. 3032000200111 2. 11.75 99. 3032000200112 2. 12. 90. 3032000200113 2. 12.25 78. 3032000200114 2. 12.5 75. 3032000200115 2. 12.75 72. 3032000200116 2. 13. 67. 3032000200117 2. 13.25 55. 3032000200118 2. 13.5 48. 3032000200119 2. 13.75 43. 3032000200120 2. 14. 40. 3032000200121 2. 14.25 35. 3032000200122 2. 14.5 33. 3032000200123 2. 14.75 31. 3032000200124 2. 15. 25. 3032000200125 2. 15.25 19. 3032000200126 2. 15.5 15. 3032000200127 2. 15.75 15. 3032000200128 2. 16. 15. 3032000200129 2. 16.25 12. 3032000200130 2. 16.5 12. 3032000200131 2. 16.75 10. 3032000200132 2. 17. 7. 3032000200133 2. 17.25 5. 3032000200134 2. 17.5 4. 3032000200135 3. 5. 1035. 3032000200136 3. 5.25 1183. 3032000200137 3. 5.5 1300. 3032000200138 3. 5.75 1383. 3032000200139 3. 6. 1479. 3032000200140 3. 6.25 1532. 3032000200141 3. 6.5 1595. 3032000200142 3. 6.75 1648. 3032000200143 3. 7. 1732. 3032000200144 3. 7.25 1796. 3032000200145 3. 7.5 1859. 3032000200146 3. 7.75 1891.5 3032000200147 3. 8. 1923.5 3032000200148 3. 8.25 1954.5 3032000200149 3. 8.5 1933.5 3032000200150 3. 8.75 1891.5 3032000200151 3. 9. 1870.5 3032000200152 3. 9.25 1838.5 3032000200153 3. 9.5 1785.5 3032000200154 3. 9.75 1690.5 3032000200155 3. 10. 1627.6 3032000200156 3. 10.25 1574.6 3032000200157 3. 10.5 1458.6 3032000200158 3. 10.75 1363.6 3032000200159 3. 11. 1310.6 3032000200160 3. 11.25 1247.6 3032000200161 3. 11.5 1162.6 3032000200162 3. 11.75 1067.6 3032000200163 3. 12. 982.63 3032000200164 3. 12.25 919.64 3032000200165 3. 12.5 835.65 3032000200166 3. 12.75 750.66 3032000200167 3. 13. 687.67 3032000200168 3. 13.25 623.68 3032000200169 3. 13.5 539.69 3032000200170 3. 13.75 475.7 3032000200171 3. 14. 454.71 3032000200172 3. 14.25 391.72 3032000200173 3. 14.5 327.73 3032000200174 3. 14.75 296.74 3032000200175 3. 15. 220.75 3032000200176 3. 15.25 243.76 3032000200177 3. 15.5 211.77 3032000200178 3. 15.75 180.78 3032000200179 3. 16. 148.79 3032000200180 3. 16.25 129.8 3032000200181 3. 16.5 116.81 3032000200182 3. 16.75 103.82 3032000200183 3. 17. 95.83 3032000200184 3. 17.25 63.84 3032000200185 3. 17.5 42.85 3032000200186 ENDDATA 155 0 3032000200187 ENDSUBENT 186 0 3032000299999 SUBENT 30320003 20100204 31443032000300001 BIB 6 15 3032000300002 REACTION (94-PU-239(N,F)ELEM/MASS,TER,FY/DE,,REL) 3032000300003 Energy spectra of He-isotopes in ternary fission 3032000300004 ANALYSIS All the spectra are sufficiently well described by a 3032000300005 Gaussian distribution. The He-isotope spectra were 3032000300006 measured for the full reactor neutron spectrum only, 3032000300007 because no fast neutron background was observed. 3032000300008 ERR-ANALYS No error given 3032000300009 COMMENT The FWHM of the energy spectra are, (in MeV) 3032000300010 4He 10.6 +- 0.2, 3032000300011 6He 10.6 +- 0.6, 3032000300012 8He larger than 9. 3032000300013 STATUS (TABLE) Data from Piasecki as priv.comm.,25/11/75, 3032000300014 corresponding to fig.2 of J,NP/A,128,219,1969 3032000300015 HISTORY (20090115S) SD 3032000300016 (20100204A) On. SF6: DE -> FY/DE, SF8: Add REL 3032000300017 ENDBIB 15 0 3032000300018 COMMON 1 3 3032000300019 ELEMENT 3032000300020 NO-DIM 3032000300021 2. 3032000300022 ENDCOMMON 3 0 3032000300023 DATA 3 78 3032000300024 MASS E DATA 3032000300025 NO-DIM MEV ARB-UNITS 3032000300026 4. 10.5 2516. 3032000300027 4. 11. 3217. 3032000300028 4. 11.5 3567. 3032000300029 4. 12. 3917. 3032000300030 4. 12.5 4363. 3032000300031 4. 13. 4904. 3032000300032 4. 13.5 5175. 3032000300033 4. 14. 5350. 3032000300034 4. 14.5 5621. 3032000300035 4. 15. 5971. 3032000300036 4. 15.5 6338. 3032000300037 4. 16. 6672. 3032000300038 4. 16.5 6863. 3032000300039 4. 17. 6688. 3032000300040 4. 17.5 6513. 3032000300041 4. 18. 6338. 3032000300042 4. 18.5 5987. 3032000300043 4. 19. 5637. 3032000300044 4. 19.5 5255. 3032000300045 4. 20. 4904. 3032000300046 4. 20.5 4363. 3032000300047 4. 21. 3933. 3032000300048 4. 21.5 3583. 3032000300049 4. 22. 3121. 3032000300050 4. 22.5 2691. 3032000300051 4. 23. 2420. 3032000300052 4. 23.5 1975. 3032000300053 4. 24. 1608. 3032000300054 4. 24.5 1433. 3032000300055 4. 25. 1162. 3032000300056 4. 25.5 908. 3032000300057 4. 26. 717. 3032000300058 4. 26.5 637. 3032000300059 4. 27. 446. 3032000300060 4. 27.5 366. 3032000300061 4. 28. 287. 3032000300062 4. 28.5 287. 3032000300063 4. 29. 175. 3032000300064 6. 11. 1428. 3032000300065 6. 11.5 1511. 3032000300066 6. 12. 1514. 3032000300067 6. 12.5 1540. 3032000300068 6. 13. 1428. 3032000300069 6. 13.5 1388. 3032000300070 6. 14. 1327. 3032000300071 6. 14.5 1227. 3032000300072 6. 15. 1129. 3032000300073 6. 15.5 1047. 3032000300074 6. 16. 946. 3032000300075 6. 16.5 845. 3032000300076 6. 17. 784. 3032000300077 6. 17.5 683. 3032000300078 6. 18. 583. 3032000300079 6. 18.5 504. 3032000300080 6. 19. 442. 3032000300081 6. 19.5 403. 3032000300082 6. 20. 324. 3032000300083 6. 20.5 241. 3032000300084 6. 21. 219. 3032000300085 6. 21.5 180. 3032000300086 6. 22. 140. 3032000300087 6. 22.5 120. 3032000300088 6. 23. 101. 3032000300089 6. 23.5 83. 3032000300090 6. 24. 61. 3032000300091 6. 24.5 55. 3032000300092 6. 25. 40. 3032000300093 6. 25.5 38. 3032000300094 6. 26. 35. 3032000300095 8. 12. 93. 3032000300096 8. 13. 91. 3032000300097 8. 14. 75. 3032000300098 8. 15. 62. 3032000300099 8. 16. 48. 3032000300100 8. 17. 36. 3032000300101 8. 18. 26. 3032000300102 8. 19. 18. 3032000300103 8. 20. 17. 3032000300104 ENDDATA 80 0 3032000300105 ENDSUBENT 104 0 3032000399999 SUBENT 30320004 20090115 31343032000400001 BIB 4 9 3032000400002 REACTION ((94-PU-239(N,F)ELEM/MASS,TER,FY)/ 3032000400003 (94-PU-239(N,F)2-HE-4,TER,FY)) 3032000400004 ANALYSIS The intensities relative to the emission of 100 alphas 3032000400005 were calculated by assuming that the low energy 3032000400006 spectrum which had not been measured, was symmetrical 3032000400007 to the corresponding high energy part. 3032000400008 STATUS (TABLE) From table 1 of Nucl.Phys.A218(1969)219. 3032000400009 ERR-ANALYS (DATA-ERR) total. The limit of the overall uncertainty3032000400010 estimated. 3032000400011 ENDBIB 9 0 3032000400012 NOCOMMON 0 0 3032000400013 DATA 4 6 3032000400014 ELEMENT MASS DATA DATA-ERR 3032000400015 NO-DIM NO-DIM NO-DIM NO-DIM 3032000400016 1. 1. 1.9000E-02 1.0000E-03 3032000400017 1. 2. 5.0000E-03 1.0000E-03 3032000400018 1. 3. 6.8000E-02 3.0000E-03 3032000400019 2. 4. 1. 3032000400020 2. 6. 1.9000E-02 2.0000E-03 3032000400021 2. 8. 8.0000E-04 2.0000E-04 3032000400022 ENDDATA 8 0 3032000400023 ENDSUBENT 22 0 3032000499999 SUBENT 30320005 20100303 31443032000500001 BIB 5 10 3032000500002 REACTION (94-PU-239(N,F)ELEM/MASS,TER,KE) 3032000500003 Peak kinetic energy. 3032000500004 ANALYSIS A Gaussian distribution was fitted to the energy 3032000500005 spectra of H-1,H-2,H-3,He-4,He-6 and He-8, by the least3032000500006 square method. 3032000500007 STATUS (TABLE) From table 1 of Nucl.Phys.A218(1969)219. 3032000500008 ERR-ANALYS (DATA-ERR) total. The limit of the overall uncertainty3032000500009 estimated. 3032000500010 HISTORY (20100303A) SD: REACTION code was changed 3032000500011 according to EXFOR rules. 3032000500012 ENDBIB 10 0 3032000500013 NOCOMMON 0 0 3032000500014 DATA 5 6 3032000500015 ELEMENT MASS DATA DATA-MAX DATA-ERR 3032000500016 NO-DIM NO-DIM MEV MEV MEV 3032000500017 1. 1. 8.4 0.15 3032000500018 1. 2. 8.2 0.3 3032000500019 1. 3. 8.2 0.15 3032000500020 2. 4. 16. 1.0000E-01 3032000500021 2. 6. 11.8 0.4 3032000500022 2. 8. 12. 3032000500023 ENDDATA 8 0 3032000500024 ENDSUBENT 23 0 3032000599999 ENDENTRY 5 0 3032099999999