ENTRY 30307 20100303 31443030700000001 SUBENT 30307001 20100303 31443030700100001 BIB 15 43 3030700100002 INSTITUTE (3INDTRM) 3030700100003 REFERENCE (J,PR/C,11,1251,197504) 3030700100004 (P,BARC-628,80,1972)Same data in table as Phys.Rev. C113030700100005 (C,73BANGLO,2,5,197312) Brief, graph only 3030700100006 AUTHOR (S.P.Dange,A.Ramaswami,S.B.Manohar,Satya Prakash, 3030700100007 M.V.Ramaniah) 3030700100008 TITLE Fragment kinetic energy distribution in the fission of 3030700100009 Np-237 by reactor neutrons. 3030700100010 FACILITY (REAC,3INDTRM) APSARA reactor 3030700100011 INC-SOURCE (REAC) Swimming pool reactor. 3030700100012 INC-SPECT Neutrons in the irradiation position used were under- 3030700100013 moderated and the neutron flux of energy above 1 MeV 3030700100014 was estimated as about 10.**11 n/cm2/sec. 3030700100015 Irradiation period varied from a few hours to 24 hours.3030700100016 SAMPLE Np-237 obtained from ORNL was purified from Am,Pu and U3030700100017 The content of Pu-239 was less than 0.004%. 3030700100018 By electrodeposition, 100 to 180 micro-gram of Np was 3030700100019 deposited over an area of 1.5 cm2 and it was covered 3030700100020 first with a stack of 1.9 mg/cm2 pure Al foil and was 3030700100021 wrapped in 63 mg/cm2 pure Al, and finally was covered 3030700100022 with about 200 mg/cm2 cadmium foil to reduce the 3030700100023 formation of Np-238. 3030700100024 METHOD (GSPEC,RCHEM) Radiochemical and gamma-ray 3030700100025 spectroscopic method. The thin-target integral range 3030700100026 measurement technique was employed to measure the 3030700100027 recoil ranges of fission products. 3030700100028 DETECTOR (GELI) Ge(Li) detector for direct counting of the 3030700100029 catcher foils on the detector. Detail, see S.P.Dange 3030700100030 et al.,2nd Int.Conf.on Phys.and Chem.of Fission,Vienna 3030700100031 1969,p.741. 3030700100032 PART-DET (FF) Fission fragments. 3030700100033 STATUS (TABLE) Data from Table 1 and p.1255 of 3030700100034 Phys.Rev.,11C(1975)1251 3030700100035 CORRECTION The average energy of a fission fragment was corrected 3030700100036 for the change in mass of emitted neutrons. (The 3030700100037 average velocity of a fragment is not changed by the 3030700100038 emission of neutrons) 3030700100039 ERR-ANALYS Errors are not given. 3030700100040 HISTORY (19750801C) KO. 3030700100041 (19821130A) ML.Conversion to reaction,changes+additions3030700100042 (20090115A) SD: BIB section updated 3030700100043 (20100303A) SD: REACTION codes in Subent were 3030700100044 changed according to EXFOR rules. 3030700100045 ENDBIB 43 0 3030700100046 COMMON 1 3 3030700100047 EN-DUMMY 3030700100048 MEV 3030700100049 1.0000E+00 3030700100050 ENDCOMMON 3 0 3030700100051 ENDSUBENT 50 0 3030700199999 SUBENT 30307002 20100303 31443030700200001 BIB 5 32 3030700200002 REACTION 1(93-NP-237(N,F)ELEM/MASS,,KE,,SPA) 3030700200003 2(93-NP-237(N,F)ELEM/MASS,,KE,,SPA) 3030700200004 Total primary kinetic energy of fission fragment. 3030700200005 ANALYSIS The recoil ranges of fission products were converted 3030700200006 into kinetic energies using two different range-energy 3030700200007 equations. They are the following: 3030700200008 1eq. of Alexander-Gazdik, Phys.Rev,120(1960)874, and 3030700200009 Phys.Rev,129(1963)259, given as 3030700200010 R = K * (E **(3/2)), R=range and E=kinetic energy, 3030700200011 and K is a constant which varies slowly with the mass. 3030700200012 2eq. of Prakash, thesis, Univ.of Bombay,1971, given as 3030700200013 R = C * ((square root(E))*(square root(A1))/((F)* 3030700200014 ((Z1)**(1/3))) 3030700200015 where the range R of a fission product of mass number 3030700200016 A1 with the most probable charge Z1 and energy E are 3030700200017 related with (F). (F) includes the light and heavy 3030700200018 primary mass numbers and their most probable charges, 3030700200019 density of the stopping medium and the electronic 3030700200020 charge. (C) is a constant. See text for detail. 3030700200021 MISC-COL (MISC1) Recoil range, in milli-gram/cm2. 3030700200022 (MISC2) 'Primary' mass of light fission fragment. 3030700200023 Accordingly, mass of heavy fragment(primary) is to be, 3030700200024 (237+1) - (primary mass of light fission fragment). 3030700200025 The 'primary' mass was obtained by adding to the mass 3030700200026 of the measured fission product the average number of 3030700200027 neutrons per fission emitted by this fragment,using 3030700200028 the neutron emission curve for Pu-239 of Apalin et al. 3030700200029 Nucl. Phys. 71,553 (1965). 3030700200030 FLAG (1.) Data obtained using Ge(Li) detector by direct 3030700200031 gamma counting only. 3030700200032 HISTORY (20100303A) SD: REACTION codes were changed 3030700200033 according to EXFOR rules. 3030700200034 ENDBIB 32 0 3030700200035 NOCOMMON 0 0 3030700200036 DATA 8 12 3030700200037 ELEMENT MASS DATA 1DATA 2MISC1 MISC1-ERR 3030700200038 MISC2 FLAG 3030700200039 NO-DIM NO-DIM MEV MEV SEE TEXT SEE TEXT 3030700200040 NO-DIM NO-DIM 3030700200041 3.8000E+01 9.1000E+01 1.7230E+02 1.6730E+02 4.1000E+00 2.0000E-023030700200042 9.2000E+01 3030700200043 4.0000E+01 9.7000E+01 1.8160E+02 1.8260E+02 4.0400E+00 8.0000E-023030700200044 9.8300E+01 3030700200045 4.2000E+01 9.9000E+01 1.8570E+02 1.8800E+02 4.0300E+00 6.0000E-023030700200046 1.0050E+02 3030700200047 4.2000E+01 9.9000E+01 1.8850E+02 1.8890E+02 4.0700E+00 8.0000E-023030700200048 1.0050E+02 1.0000E+00 3030700200049 4.5000E+01 1.0500E+02 1.8500E+02 1.7790E+02 3.8500E+00 3.0000E-023030700200050 1.0660E+02 3030700200051 4.7000E+01 1.1100E+02 1.7550E+02 1.7270E+02 3.5300E+00 1.0000E-023030700200052 1.1350E+02 3030700200053 4.8000E+01 1.1500E+02 1.6750E+02 1.6450E+02 3.3200E+00 6.0000E-023030700200054 1.1780E+02 3030700200055 5.1000E+01 1.2700E+02 1.8120E+02 1.8780E+02 3.3100E+00 1.0000E-023030700200056 1.1030E+02 3030700200057 5.2000E+01 1.3200E+02 1.7830E+02 1.8730E+02 3.1900E+00 2.0000E-023030700200058 1.0530E+02 3030700200059 5.2000E+01 1.3200E+02 1.8680E+02 1.9440E+02 3.2900E+00 2.0000E-023030700200060 1.0530E+02 1.0000E+00 3030700200061 5.4000E+01 1.3500E+02 1.8510E+02 2.0070E+02 3.2200E+00 2.0000E-023030700200062 1.0200E+02 3030700200063 5.6000E+01 1.4000E+02 1.7450E+02 1.9560E+02 3.0300E+00 4.0000E-023030700200064 9.6400E+01 3030700200065 ENDDATA 28 0 3030700200066 ENDSUBENT 65 0 3030700299999 ENDENTRY 2 0 3030799999999