ENTRY 22102 20211229 23062210200000001 SUBENT 22102001 20211229 23062210200100001 BIB 9 33 2210200100002 TITLE Measurement of 14N(n,t)12C reaction cross section in 2210200100003 the energy range of 5.0 to 10.6 MeV 2210200100004 AUTHOR (A.Suhaimi,R.Woelfle,S.M.Qaim,P.Warwick,d G.Stoecklin) 2210200100005 REFERENCE (J,RCA,43,133,1988) final publ. of 14N(n,t)12C reaction2210200100006 (R,JUEL-2196,1988) 2210200100007 (C,88MITO,,225,1988) 2210200100008 REL-REF (O,22068001,A.Suhaimi+,J,RCA,40,113,1986) - 2210200100009 10B(n,t)2alpha reaction 2210200100010 INSTITUTE (2GERJUL) 2210200100011 METHOD (CHSEP) Tritium counting techniques. 2210200100012 Tritium was separated from the irradiated samples 2210200100013 by vacuum extraction and measured in the gas phase 2210200100014 using anticoincidence proportional counting. 2210200100015 DETECTOR (PROPC) A 31 mm diameter cylindrical gas-filled counter2210200100016 (FZ35) was used for absolute tritium activity measure-2210200100017 ments. The counter had an effective counting volume of2210200100018 85 cm3 and a dead volume of 15 cm3. Low level counting2210200100019 was performed by placing the counter inside a ring 2210200100020 type gas counting tube (RZ/500) housed within a lead 2210200100021 shield. The two detectors were used in an anticoinci- 2210200100022 dence mode. 2210200100023 (GELI) Geli detector used for measurement of gamma- 2210200100024 rays from the monitor foils. 2210200100025 CORRECTION Corrections were applied for background neutrons from 2210200100026 the target construction material and from the d-d 2210200100027 breakup reaction. Corrections were also applied for 2210200100028 tritium loss due to residual tritium in the sample. 2210200100029 HISTORY (19881102C) N.O. 2210200100030 (19890531U) IF. Page of reference added 2210200100031 (20211229A) SD:Updated to new date formats,lower case. 2210200100032 Corrections in All Subents. Entry updated according 2210200100033 final publ.: RCA,43,133,1988. Subent 003 deleted 2210200100034 duplication with 22068.002. Subent 005 added. 2210200100035 ENDBIB 33 0 2210200100036 NOCOMMON 0 0 2210200100037 ENDSUBENT 36 0 2210200199999 SUBENT 22102002 20211229 23062210200200001 BIB 8 53 2210200200002 REACTION (7-N-14(N,T)6-C-12,,SIG) 2210200200003 FACILITY (CYCLO,2GERJUL) For the boron and nitrogen measurements2210200200004 deuterons were accelerated to 3.0 - 8.0 MeV with a 2210200200005 Compact Cyclotron, CV 28. 2210200200006 INC-SOURCE (D-D) Neutrons in the energy range 2.5 to 10.6 MeV were2210200200007 produced with a deuterium gas target, having an 2210200200008 entrance havar foil of 7 um thickness. 2210200200009 The gas cell had a length of 3.7 cm and a diameter 2210200200010 of 4.0 cm, with wall thicknesses of 0.1 cm, or a 2210200200011 niobium entrance foil of 6.5, 20.0 or 50.0 um 2210200200012 thickness and a molybdenum beam stop. The gas cell had2210200200013 a length of 3.7 cm and a diameter of 4.0 cm, with wall2210200200014 thicknesses of 0.1 cm made of brass. 2210200200015 The mean neutron flux densities were of the 2210200200016 order of 1.0E+07 n/cm2sec. 2210200200017 MONITOR (28-NI-58(N,P)27-CO-58,,SIG) 2210200200018 (26-FE-54(N,P)25-MN-54,,SIG) 2210200200019 SAMPLE The nitrogen samples consisted of between 9 and 15 g 2210200200020 of degassed aluminium-nitride (ALN) powder (chemical 2210200200021 purity greater than 98%, grain size less than 10 um) 2210200200022 pressed in a polyethylene capsule, 24.5 mm diameter 2210200200023 and up to 25.0 mm long. Lithium and boron impurities 2210200200024 in the sample was determined with neutron activation 2210200200025 analysis. 2210200200026 ERR-ANALYS (ERR-T) Total errors, composed of the following 2210200200027 contributions. 2210200200028 (ERR-1) Uncertainty in weight of monitors and foils 2210200200029 (ERR-2) Uncertainty in irradiation time 2210200200030 (ERR-3,1.,2.) Uncertainty in half-life dependent 2210200200031 effects 2210200200032 (ERR-4) Uncertainty in neutron source characteristics 2210200200033 (ERR-5) Uncertainty in irradiation geometry 2210200200034 (ERR-6,0.2,15.) Uncertainty in correction for activity 2210200200035 induced by background neutrons (gas out/in, breakup) 2210200200036 (ERR-7) Uncertainty in correction for absorption and 2210200200037 scattering of neutrons in the sample 2210200200038 (ERR-8) Error in excitation function of monitor 2210200200039 reaction 2210200200040 (ERR-9,4.,6.) Uncertainty in determination of detector 2210200200041 counts 2210200200042 (ERR-10,,1.) Uncertainty in absorption of gamma-ray in 2210200200043 the monitors 2210200200044 (ERR-11) Uncertainty in efficiency of the gamma 2210200200045 detector 2210200200046 (ERR-12) Uncertainty in efficiency of gas counting tube2210200200047 (ERR-13) Uncertainty in separation yield 2210200200048 (ERR-14,1.,4.) Uncertainty in stopping power/gas 2210200200049 filled target 2210200200050 (ERR-15) Uncertainty of plateau 2210200200051 (ERR-16) Uncertainty in 14C removal 2210200200052 STATUS (TABLE) Tbl.1 from Radiochimica Acta 43(1988)133 2210200200053 Uncertainties are from Tbl.8 of JUEL-2196 2210200200054 HISTORY (20211229U) SD: BIB updated. 2210200200055 ENDBIB 53 0 2210200200056 COMMON 11 6 2210200200057 ERR-1 ERR-2 ERR-4 ERR-5 ERR-7 ERR-8 2210200200058 ERR-11 ERR-12 ERR-13 ERR-15 ERR-16 2210200200059 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2210200200060 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2210200200061 0.1 0.1 3. 3. 5. 8. 2210200200062 3. 4. 4. 3. 4. 2210200200063 ENDCOMMON 6 0 2210200200064 DATA 4 16 2210200200065 EN EN-RSL DATA ERR-T 2210200200066 MEV MEV MB MB 2210200200067 5.02 0.16 23. 3. 2210200200068 5.57 0.17 18. 3. 2210200200069 5.67 0.17 28. 4. 2210200200070 6.05 0.17 26. 4. 2210200200071 6.29 0.18 20. 3. 2210200200072 6.59 0.16 30. 5. 2210200200073 7.10 0.18 21. 3. 2210200200074 7.61 0.19 17. 3. 2210200200075 8.11 0.20 17. 3. 2210200200076 8.50 0.21 20. 3. 2210200200077 8.61 0.22 19. 3. 2210200200078 8.93 0.27 22. 4. 2210200200079 9.03 0.26 12. 2. 2210200200080 9.61 0.23 16. 3. 2210200200081 10.08 0.24 11. 2. 2210200200082 10.57 0.25 14. 2. 2210200200083 ENDDATA 18 0 2210200200084 ENDSUBENT 83 0 2210200299999 NOSUBENT 22102003 20211229 23062210200300001 SUBENT 22102004 20211229 23062210200400001 BIB 10 18 2210200400002 REACTION (5-B-10(N,T+A)2-HE-4,,SIG,,SPA) 2210200400003 FACILITY (REAC,2GERJUL) the thermal cross section for boron was 2210200400004 determined using the DIDO reactor. 2210200400005 MONITOR (30-ZN-64(N,G)30-ZN-65,,SIG,,SPA) 2210200400006 SAMPLE For irradiations at the reactor B2O3 powder was mixed 2210200400007 with ZnO powder and contained in 3 mm diameter by 2210200400008 40 mm long quartz ampoules. The ZnO was used as an 2210200400009 internal flux monitor. The samples were irradiated for2210200400010 22 hours. 2210200400011 INC-SOURCE (THCOL) The thermal column of FRJ-2 was used to obtain 2210200400012 a thermal flux densitiy of the order of 2210200400013 2 x 1.0E+12 n/cm2/sec for determining the thermal 2210200400014 cross section of boron. 2210200400015 INC-SPECT Neutrons from the thermal column of FRJ-2 reactor. 2210200400016 ERR-ANALYS (DATA-ERR) No information about source of uncertainty 2210200400017 STATUS (TABLE) Text on p.226 of 88MITO,p.225,1988 2210200400018 COMMENT Value 11.9+-2.4 mb is given on p.99 of JUEL-2196,1988 2210200400019 HISTORY (20211229A) SD: BIB and DATA col. updated. MONIT added.2210200400020 ENDBIB 18 0 2210200400021 NOCOMMON 0 0 2210200400022 DATA 5 1 2210200400023 EN-DUMMY DATA DATA-ERR MONIT MONIT-ERR 2210200400024 EV MB MB MB MB 2210200400025 2.530E-02 12.0 2.5 780. 20. 2210200400026 ENDDATA 3 0 2210200400027 ENDSUBENT 26 0 2210200499999 SUBENT 22102005 20211229 23062210200500001 BIB 8 41 2210200500002 REACTION (4-BE-9(N,T)3-LI-7,,SIG) 2210200500003 FACILITY (CYCLO,2GERJUL) For the boron and nitrogen measurements2210200500004 deuterons were accelerated to 3.0 - 8.0 MeV with a 2210200500005 Compact Cyclotron, CV28. 2210200500006 INC-SOURCE (D-D) Neutrons in the energy range 2.5 to 10.6 MeV were2210200500007 produced with a deuterium gas target, having an 2210200500008 entrance havar foil of 7 um thickness. 2210200500009 The gas cell had a length of 3.7 cm and a diameter 2210200500010 of 4.0 cm, with wall thicknesses of 0.1 cm, or a 2210200500011 niobium entrance foil of 6.5, 20.0 or 50.0 um 2210200500012 thickness and a molybdenum beam stop. The gas cell had2210200500013 a length of 3.7 cm and a diameter of 4.0 cm, with wall2210200500014 thicknesses of 0.1 cm made of brass. 2210200500015 The mean neutron flux densities were of the 2210200500016 order of 1.0E+07 n/cm2sec. 2210200500017 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2210200500018 SAMPLE High purity Be sheets (10 x 10 x 5 mm) 2210200500019 ERR-ANALYS (ERR-T) Total errors, composed of the following 2210200500020 contributions. 2210200500021 (ERR-1) Uncertainty in weight of monitors and foils 2210200500022 (ERR-2) Uncertainty in irradiation time 2210200500023 (ERR-3,1.,2.) Uncertainty in half-life dependent 2210200500024 effects 2210200500025 (ERR-4) Uncertainty in neutron source characteristics 2210200500026 (ERR-5) Uncertainty in irradiation geometry 2210200500027 (ERR-6,,2.) Uncertainty in correction for absorption an2210200500028 scattering of neutrons in the sample 2210200500029 (ERR-7,8.,15.) Error in excitation function of monitor 2210200500030 reaction 2210200500031 (ERR-8,4.,6.) Uncertainty in determination of detector 2210200500032 counts 2210200500033 (ERR-9,,1.) Uncertainty in absorption of gamma-ray in 2210200500034 the monitors 2210200500035 (ERR-10) Uncertainty in efficiency of the gamma 2210200500036 detector 2210200500037 (ERR-11) Uncertainty in efficiency of gas counting tube2210200500038 (ERR-12) Uncertainty in separation yield 2210200500039 (ERR-13) Uncertainty of plateau 2210200500040 STATUS (TABLE) Tbl.2 of Radiochimica Acta 43(1988)133 2210200500041 In Tbl. 8,11 from JUEL-2196 prelim.data + uncertainty 2210200500042 HISTORY (20211229C) SD 2210200500043 ENDBIB 41 0 2210200500044 COMMON 8 6 2210200500045 ERR-1 ERR-2 ERR-4 ERR-5 ERR-10 ERR-11 2210200500046 ERR-12 ERR-13 2210200500047 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2210200500048 PER-CENT PER-CENT 2210200500049 0.1 0.1 4. 3. 3. 4.2210200500050 4. 3. 2210200500051 ENDCOMMON 6 0 2210200500052 DATA 3 6 2210200500053 EN DATA ERR-T 2210200500054 MEV MB MB 2210200500055 17.5 3.2 0.4 2210200500056 20.0 4.6 0.7 2210200500057 22.5 6.3 1.1 2210200500058 25.0 8.6 1.5 2210200500059 27.5 11.0 2.0 2210200500060 30.0 13.5 2.6 2210200500061 ENDDATA 8 0 2210200500062 ENDSUBENT 61 0 2210200599999 ENDENTRY 5 0 2210299999999