ENTRY 21467 19801104 00002146700000001 SUBENT 21467001 19801104 00002146700100001 BIB 13 25 2146700100002 INSTITUTE (2UK HAR) 2146700100003 REFERENCE (J,JIN,30,897,6805) MAIN REFERENCE 2146700100004 (R,AERE-R-5520,6707) 2146700100005 (R,AERE-R-6384,7005) 2146700100006 AUTHOR (M.J.CABELL,M.WILKINS) 2146700100007 TITLE -MASS SPECTROMETRIC MEASUREMENTS OF THE NEUTRON 2146700100008 CAPTURE CROSS SECTIONS OF ND-142, ND-143, ND-144 2146700100009 AND ND-145 FOR REACTOR AND MAXWELLIAN NEUTRONS. 2146700100010 FACILITY (REAC ) PLUTO REACTOR AT HARWELL 2146700100011 (SPECM) TYPE M.S.5 MASS SPECTROMETER. 2146700100012 INC-SOURCE (REAC ) DOSE RANGE FROM 1.018E+21 TO 1.942E+21 N/CM2 2146700100013 SAMPLE .13 MG OF ND-BEARING SILICA (APPROX. 150 MICROGRAM ND) 2146700100014 SEALED IN A SMALL SILICA PHIAL. ISOTOPIC COMPOSITION 2146700100015 GIVEN IN TABLE 3. 2146700100016 METHOD (ASEP ) SEPARATION BY MASS SEPARATOR 2146700100017 DETECTOR (MAGSP) MAGNETIC SPECTROMETER 2146700100018 MONITOR (27-CO-59(N,G)27-CO-60-G,,SIG) THE THERMAL CAPTURE 2146700100019 CROSS SECTION. 2146700100020 (27-CO-59(N,G)27-CO-60-G,,RI) 2146700100021 STATUS .DATA TAKEN FROM MAIN REFERENCE. 2146700100022 HISTORY (800215C) JR 2146700100023 (800331E) 2146700100024 ERR-ANALYS .SYSTEMATIC ERRORS IN NEUTRON DOSE,ATOMIC RATIOS AND 2146700100025 THE NEUTRON CAPTURE CROSS SECTION OF 2146700100026 THE OTHER NEODYMIUM ISOTOPES. 2146700100027 ENDBIB 25 0 2146700100028 COMMON 4 3 2146700100029 MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 2146700100030 B B B B 2146700100031 3.7400E+01 6.0000E-01 7.2600E+01 4.6000E+00 2146700100032 ENDCOMMON 3 0 2146700100033 ENDSUBENT 32 0 2146700199999 SUBENT 21467002 19801104 00002146700200001 BIB 3 4 2146700200002 REACTION (60-ND-142(N,G)60-ND-143,,SIG,,MXW) 2146700200003 INC-SPECT MAXWELLIAN NEUTRONS WITH A TEMPERATURE 2146700200004 T = 82 +- 13 DEG-C. 2146700200005 STATUS DATA TAKEN FROM TEXT IN MAIN REFERENCE. 2146700200006 ENDBIB 4 0 2146700200007 NOCOMMON 0 0 2146700200008 DATA 3 1 2146700200009 EN-DUMMY DATA DATA-ERR 2146700200010 EV B B 2146700200011 2.5300E-02 1.8760E+01 7.3000E-01 2146700200012 ENDDATA 3 0 2146700200013 ENDSUBENT 12 0 2146700299999 SUBENT 21467003 19801104 00002146700300001 BIB 3 4 2146700300002 REACTION (60-ND-143(N,G)60-ND-144,,SIG,,MXW) 2146700300003 INC-SPECT MAXWELLIAN NEUTRONS WITH A TEMPERATURE 2146700300004 T = 82+-13 DEG-C 2146700300005 STATUS DATA TAKEN FROM TEXT IN MAIN REF. 2146700300006 ENDBIB 4 0 2146700300007 NOCOMMON 0 0 2146700300008 DATA 3 1 2146700300009 EN-DUMMY DATA DATA-ERR 2146700300010 EV B B 2146700300011 2.5300E-02 3.1610E+02 1.3500E+01 2146700300012 ENDDATA 3 0 2146700300013 ENDSUBENT 12 0 2146700399999 SUBENT 21467004 19801104 00002146700400001 BIB 3 4 2146700400002 REACTION (60-ND-144(N,G)60-ND-145,,SIG,,MXW) 2146700400003 INC-SPECT MAXWELLIAN NEUTRONS OF A TEMPERATURE 2146700400004 T = 82+-13 DEG-C 2146700400005 STATUS DATA TAKEN FROM TEXT IN MAIN REFERENCE. 2146700400006 ENDBIB 4 0 2146700400007 NOCOMMON 0 0 2146700400008 DATA 3 1 2146700400009 EN-DUMMY DATA DATA-ERR 2146700400010 EV B B 2146700400011 2.5300E-02 3.5800E+00 3.1000E-01 2146700400012 ENDDATA 3 0 2146700400013 ENDSUBENT 12 0 2146700499999 SUBENT 21467005 19801104 00002146700500001 BIB 4 8 2146700500002 REACTION (60-ND-145(N,G)60-ND-146,,SIG,,MXW) 2146700500003 INC-SPECT MAXWELLIAN NEUTRONS OF A TEMPERATURE 2146700500004 T = 82+-13 DEG-C 2146700500005 ASSUMED (ASSUM,60-ND-146(N,G)60-ND-147,,SIG) WESTCOTT S-0 2146700500006 FOR ND-146 ASSUMED TO BE 2.1+-0.4. 2146700500007 VALUE REFERS TO THERMAL ENERGY. 2146700500008 ASSUMED VALUES TAKEN FROM JIN,29,2155,1967. 2146700500009 STATUS .DATA TAKEN FROM MAIN REFERENCE 2146700500010 ENDBIB 8 0 2146700500011 COMMON 2 3 2146700500012 ASSUM ASSUM-ERR 2146700500013 B B 2146700500014 1.3000E+00 1.0000E-01 2146700500015 ENDCOMMON 3 0 2146700500016 DATA 3 1 2146700500017 EN-DUMMY DATA DATA-ERR 2146700500018 EV B B 2146700500019 2.5300E-02 4.2100E+01 2.2000E+00 2146700500020 ENDDATA 3 0 2146700500021 ENDSUBENT 20 0 2146700599999 SUBENT 21467006 19800331 00002146700600001 BIB 2 2 2146700600002 REACTION (60-ND-143(N,G)60-ND-144,,SIG) 2146700600003 STATUS .DATA TAKEN FROM TEXT IN MAIN REFERENCE 2146700600004 ENDBIB 2 0 2146700600005 NOCOMMON 0 0 2146700600006 DATA 3 1 2146700600007 EN DATA DATA-ERR 2146700600008 EV B B 2146700600009 2.5300E-02 3.1800E+02 1.3600E+01 2146700600010 ENDDATA 3 0 2146700600011 ENDSUBENT 10 0 2146700699999 SUBENT 21467007 19800331 00002146700700001 BIB 3 5 2146700700002 REACTION (60-ND-145(N,G)60-ND-146,,SIG) 2146700700003 ASSUMED (ASSUM,60-ND-146(N,G)60-ND-147,,SIG) WESTCOTT S-0 2146700700004 FOR ND-146 ASSUMED TO BE 2.1+-0.4. 2146700700005 ASSUMED VALUES TAKEN FROM JIN,29,2155,1967. 2146700700006 STATUS .DATA TAKEN FROM TEXT IN MAIN REFERENCE 2146700700007 ENDBIB 5 0 2146700700008 COMMON 3 3 2146700700009 EN ASSUM ASSUM-ERR 2146700700010 EV B B 2146700700011 2.5300E-02 1.3000E+00 1.0000E-01 2146700700012 ENDCOMMON 3 0 2146700700013 DATA 2 1 2146700700014 DATA DATA-ERR 2146700700015 B B 2146700700016 4.0500E+01 2.1000E+00 2146700700017 ENDDATA 3 0 2146700700018 ENDSUBENT 17 0 2146700799999 ENDENTRY 7 0 2146799999999