ENTRY 21651 20101114 22252165100000001 SUBENT 21651001 20101114 22252165100100001 BIB 15 38 2165100100002 INSTITUTE (2BLGGHT) H.T.,E.J.,P.D.,D.D,a.D.,P.D.,A.J.D. 2165100100003 (2FR ILL) Experimental site, j.B.,P.P. 2165100100004 REFERENCE (J,NP/A,342,229,198006) 2165100100005 (W,JACOBS,19800924) Private communication from 2165100100006 E.Jacobs with the numerical data of the neutron 2165100100007 emission curve of fig. 2 Of NP/A,342,229(1980). 2165100100008 AUTHOR (H.Thierens,E.Jacobs,P.D'hondt,D.De Frenne, 2165100100009 A.De Clercq,P.De Gelder,A.J.Deruytter,J.Blachot, 2165100100010 P.Perrin) 2165100100011 TITLE -The thermal neutron sub-barrier fission of Np-237.- 2165100100012 FACILITY (REAC,2FR ILL) Inclined beam hole IH1 of the 2165100100013 ILL high flux reactor. Thermal flux of 5. x 10**9 2165100100014 n/cm**2/sec, Cd-ratio of 1. x 10**4. 2165100100015 INC-SOURCE (REAC ) Reactor. 2165100100016 INC-SPECT .Thermal Maxwellian spectrum from HFR. 2165100100017 SAMPLE .Prepared at CBNM,Geel, 30 mg/cm**2, 25 cm diam, 2165100100018 on Al-disk. Ultrapure Np(x)-O(Y) was used 2165100100019 (impurity less than 5 ppm). catcher foil of 2165100100020 99.999% pure Al. 2165100100021 METHOD .Catcher foil technique. 2165100100022 .The fission products caught in the foil are 2165100100023 gamma counted. 2165100100024 DETECTOR (GELI ) 50 CC Ge(Li) detector, 2.4 keV 2165100100025 resolution at 1333. keV. 2165100100026 PART-DET (DG ) Decay gammas. 2165100100027 CORRECTION .Charge distribution correction. 2165100100028 ERR-ANALYS (DATA-ERR) Total error is given. Details 2165100100029 are not given. 2165100100030 STATUS .Compiled from Nucl.Phys. A342,229,1980. 2165100100031 HISTORY (19800912C) G.C. 2165100100032 (19801015E) 2165100100033 (19820115A) One element in subent 004 corrected. 2165100100034 (19820217E) 2165100100035 (19820225A) A.P.T. Reaction in subent 004 corrected. 2165100100036 (19820921E) 2165100100037 (20101114A) SD:Updated to new date formats,lower case. 2165100100038 corrected according to last EXFOR rules and Dict. 2165100100039 ref. in REL-REF in Subent 006 corrected. 2165100100040 ENDBIB 38 0 2165100100041 COMMON 1 3 2165100100042 EN-DUMMY 2165100100043 EV 2165100100044 2.5300E-02 2165100100045 ENDCOMMON 3 0 2165100100046 ENDSUBENT 45 0 2165100199999 SUBENT 21651002 20101114 22252165100200001 BIB 2 2 2165100200002 REACTION (93-NP-237(N,F)MASS,CHN,FY,,MXW) 2165100200003 STATUS (TABLE) from table 1 from Nucl.Phys. A342,229,1980. 2165100200004 ENDBIB 2 0 2165100200005 NOCOMMON 0 0 2165100200006 DATA 3 32 2165100200007 MASS DATA DATA-ERR 2165100200008 NO-DIM PC/FIS PC/FIS 2165100200009 8.5000E+01 1.0400E+00 8.0000E-02 2165100200010 8.7000E+01 1.8800E+00 1.6000E-01 2165100200011 8.8000E+01 2.2400E+00 1.7000E-01 2165100200012 9.1000E+01 3.6700E+00 2.6000E-01 2165100200013 9.2000E+01 4.1800E+00 2.4000E-01 2165100200014 9.3000E+01 4.8000E+00 4.5000E-01 2165100200015 9.4000E+01 5.0200E+00 5.5000E-01 2165100200016 9.5000E+01 5.7200E+00 4.4000E-01 2165100200017 9.7000E+01 5.8800E+00 2.9000E-01 2165100200018 9.9000E+01 6.6500E+00 3.7000E-01 2165100200019 1.0100E+02 6.8000E+00 6.2000E-01 2165100200020 1.0300E+02 5.8700E+00 4.3000E-01 2165100200021 1.0400E+02 3.8900E+00 2.9000E-01 2165100200022 1.0500E+02 2.6000E+00 2.5000E-01 2165100200023 1.1500E+02 1.3100E-02 1.2000E-03 2165100200024 1.2700E+02 1.7000E-01 4.0000E-02 2165100200025 1.2900E+02 9.9000E-01 1.3000E-01 2165100200026 1.3100E+02 3.5100E+00 2.8000E-01 2165100200027 1.3200E+02 4.3000E+00 3.4000E-01 2165100200028 1.3300E+02 6.5500E+00 3.6000E-01 2165100200029 1.3400E+02 6.6200E+00 5.5000E-01 2165100200030 1.3500E+02 7.7700E+00 3.5000E-01 2165100200031 1.3800E+02 6.2300E+00 3.8000E-01 2165100200032 1.4000E+02 6.1100E+00 4.0000E-01 2165100200033 1.4100E+02 6.1400E+00 4.7000E-01 2165100200034 1.4200E+02 5.0300E+00 4.0000E-01 2165100200035 1.4300E+02 5.1000E+00 3.7000E-01 2165100200036 1.4600E+02 2.8700E+00 3.6000E-01 2165100200037 1.4700E+02 2.5700E+00 2.1000E-01 2165100200038 1.4900E+02 1.7000E+00 2.5000E-01 2165100200039 1.5100E+02 8.1000E-01 1.2000E-01 2165100200040 1.5600E+02 1.2000E-01 4.0000E-02 2165100200041 ENDDATA 34 0 2165100200042 ENDSUBENT 41 0 2165100299999 SUBENT 21651003 20101114 22252165100300001 BIB 2 2 2165100300002 REACTION (93-NP-237(N,F),,NU,,MXW) Total nu-bar. 2165100300003 STATUS (TABLE) from table 2 from Nucl.Phys. A342,229,1980. 2165100300004 ENDBIB 2 0 2165100300005 NOCOMMON 0 0 2165100300006 DATA 2 1 2165100300007 DATA DATA-ERR 2165100300008 PRT/FIS PRT/FIS 2165100300009 2.4700E+00 1.4000E-01 2165100300010 ENDDATA 3 0 2165100300011 ENDSUBENT 10 0 2165100399999 SUBENT 21651004 20101114 22252165100400001 BIB 4 8 2165100400002 REACTION ((93-NP-237(N,F)ELEM/MASS,IND,FY,,MXW)/ 2165100400003 (93-NP-237(N,F)MASS,CHN,FY,,MXW)) 2165100400004 RESULT (FRIND) 2165100400005 STATUS (TABLE) from table 3 from Nucl.Phys. A342,229,1980. 2165100400006 HISTORY (19820115A) One element corrected. 2165100400007 (19820217E) 2165100400008 (19820225A) A.P.T. Reaction corrected. 2165100400009 (19820921E) 2165100400010 ENDBIB 8 0 2165100400011 NOCOMMON 0 0 2165100400012 DATA 4 2 2165100400013 ELEMENT MASS DATA DATA-ERR 2165100400014 NO-DIM NO-DIM NO-DIM NO-DIM 2165100400015 5.3000E+01 1.3400E+02 3.2600E-01 7.4000E-02 2165100400016 5.4000E+01 1.3500E+02 1.0200E-01 1.8000E-02 2165100400017 ENDDATA 4 0 2165100400018 ENDSUBENT 17 0 2165100499999 SUBENT 21651005 20101114 22252165100500001 BIB 2 3 2165100500002 REACTION (93-NP-237(N,F)MASS,,ZP,,MXW) Most probable charge. 2165100500003 STATUS (TABLE) from table 3 from Nucl.Phys. A342,229,1980. 2165100500004 (DEP,21651002) 2165100500005 ENDBIB 3 0 2165100500006 NOCOMMON 0 0 2165100500007 DATA 4 2 2165100500008 MASS DATA -DATA-ERR +DATA-ERR 2165100500009 NO-DIM NO-DIM NO-DIM NO-DIM 2165100500010 1.3400E+02 5.2280E+01 1.7000E-01 1.2000E-01 2165100500011 1.3500E+02 5.2790E+01 1.4000E-01 1.3000E-01 2165100500012 ENDDATA 4 0 2165100500013 ENDSUBENT 12 0 2165100599999 SUBENT 21651006 20101114 22252165100600001 BIB 4 12 2165100600002 REACTION (93-NP-237(N,F)MASS,PR,NU,,MXW) Total neutron emission 2165100600003 curve as a function of the pre-neutron fragment 2165100600004 mass. 2165100600005 REL-REF (R,21543001,Asghar+,J,NP/A,292,225,1977) 2165100600006 The energy correlation data measured in that work 2165100600007 are used in conjunction with the measured post- 2165100600008 neutron mass distribution of the Nucl.Phys. A342, 2165100600009 p.229 (1980) to calculate the emission curve. 2165100600010 (M,,E.Jacobs+,J,PR/C,14,1874,1976) 2165100600011 (M,,J.Terrell+,J,PR,127,880,1962) 2165100600012 STATUS (TABLE) .Data from private communication of E.Jacobs. 2165100600013 HISTORY (20101117A) SD: SF5 in REACTION corrected (PAR => PR) 2165100600014 ENDBIB 12 0 2165100600015 NOCOMMON 0 0 2165100600016 DATA 3 47 2165100600017 MASS DATA DATA-ERR 2165100600018 NO-DIM PRT/FIS PRT/FIS 2165100600019 8.5000E+01 1.0000E-01 5.2000E-01 2165100600020 8.6000E+01 2.4000E-01 4.8000E-01 2165100600021 8.7000E+01 3.6000E-01 4.5000E-01 2165100600022 8.8000E+01 5.0000E-01 4.7000E-01 2165100600023 8.9000E+01 5.8000E-01 4.5000E-01 2165100600024 9.0000E+01 6.8000E-01 4.4000E-01 2165100600025 9.1000E+01 7.6000E-01 4.3000E-01 2165100600026 9.2000E+01 8.1000E-01 4.3000E-01 2165100600027 9.3000E+01 8.3000E-01 4.1000E-01 2165100600028 9.4000E+01 8.6000E-01 4.0000E-01 2165100600029 9.5000E+01 9.1000E-01 3.9000E-01 2165100600030 9.6000E+01 9.5000E-01 3.9000E-01 2165100600031 9.7000E+01 1.0100E+00 3.8000E-01 2165100600032 9.8000E+01 1.0800E+00 3.8000E-01 2165100600033 9.9000E+01 1.1700E+00 3.7000E-01 2165100600034 1.0000E+02 1.2500E+00 3.7000E-01 2165100600035 1.0100E+02 1.3500E+00 3.6000E-01 2165100600036 1.0200E+02 1.4800E+00 3.6000E-01 2165100600037 1.0300E+02 1.6100E+00 3.6000E-01 2165100600038 1.0400E+02 1.7900E+00 3.6000E-01 2165100600039 1.0500E+02 2.0100E+00 3.7000E-01 2165100600040 1.0600E+02 2.2900E+00 4.5000E-01 2165100600041 1.0700E+02 2.5900E+00 4.4000E-01 2165100600042 1.0800E+02 2.8400E+00 6.4000E-01 2165100600043 1.3200E+02 1.2000E-01 4.4000E-01 2165100600044 1.3300E+02 3.0000E-01 3.4000E-01 2165100600045 1.3400E+02 5.5000E-01 3.5000E-01 2165100600046 1.3500E+02 6.8000E-01 3.7000E-01 2165100600047 1.3600E+02 8.7000E-01 3.4000E-01 2165100600048 1.3700E+02 1.0100E+00 3.7000E-01 2165100600049 1.3800E+02 1.0900E+00 3.7000E-01 2165100600050 1.3900E+02 1.1700E+00 3.7000E-01 2165100600051 1.4000E+02 1.2500E+00 3.7000E-01 2165100600052 1.4100E+02 1.3300E+00 3.8000E-01 2165100600053 1.4200E+02 1.4000E+00 3.8000E-01 2165100600054 1.4300E+02 1.5200E+00 3.8000E-01 2165100600055 1.4400E+02 1.5300E+00 4.0000E-01 2165100600056 1.4500E+02 1.6300E+00 4.0000E-01 2165100600057 1.4600E+02 1.7100E+00 4.1000E-01 2165100600058 1.4700E+02 1.7800E+00 4.2000E-01 2165100600059 1.4800E+02 1.8500E+00 4.3000E-01 2165100600060 1.4900E+02 1.9500E+00 4.4000E-01 2165100600061 1.5000E+02 2.0600E+00 4.6000E-01 2165100600062 1.5100E+02 2.2000E+00 4.6000E-01 2165100600063 1.5200E+02 2.4200E+00 4.8000E-01 2165100600064 1.5300E+02 2.5700E+00 4.6000E-01 2165100600065 1.5400E+02 2.6900E+00 4.6000E-01 2165100600066 ENDDATA 49 0 2165100600067 ENDSUBENT 66 0 2165100699999 ENDENTRY 6 0 2165199999999