ENTRY O2466 20200408 O078O246600000001 SUBENT O2466001 20200408 O078O246600100001 BIB 8 22 O246600100002 TITLE A nuclear simulation experiment for the International O246600100003 Fusion Materials Irradiation Facility (IFMIF) O246600100004 AUTHOR (U.Von Mollendorff,F.Maekawa,H.Giese,H.Feuerstein) O246600100005 INSTITUTE (2GERKFK,2JPNJAE) O246600100006 REFERENCE (R,FZKA-6764,2002) O246600100007 FACILITY (ISOCY,2GERKFK) 3 muA deuteron beam of 52 MeV and 2.5 O246600100008 mm diameter incident on an internal target. O246600100009 METHOD (INTB,BCINT) Beam current was registered by a O246600100010 calibrated current-to-frequency converter. It was O246600100011 corrected for the effect of deuterons absorption in O246600100012 the steel target entrance wall assuming that only (85 O246600100013 +/- 5) % of the beam deuterons have reached the O246600100014 lithium. O246600100015 SAMPLE Metallic natural lithium of 21.8 mm thickness was O246600100016 enclosed in a stainless steel container (the drawing O246600100017 of the target is available in reference). The O246600100018 upstream 1.1 mm thick side of container takes away 12 O246600100019 MeV. Target was positioned inside the cyclotron O246600100020 magnet gap and was cooled by water. A separate O246600100021 measurement with empty steel container was made to O246600100022 subtract the neutron background. O246600100023 HISTORY (20200408C) Compiled by SS. O246600100024 ENDBIB 22 0 O246600100025 COMMON 1 3 O246600100026 EN O246600100027 MEV O246600100028 40. O246600100029 ENDCOMMON 3 0 O246600100030 ENDSUBENT 29 0 O246600199999 SUBENT O2466002 20200408 O078O246600200001 BIB 7 21 O246600200002 REACTION (3-LI-0(D,X)1-H-3,,PY,,TT) O246600200003 DECAY-DATA (1-H-3,12.3YR,B-) O246600200004 METHOD (ACTIV) The tritium in the irradiated lithium target O246600200005 was measured by releasing it from the target at O246600200006 several hundred degrees Celsius within a quartz tube O246600200007 through which a gas stream of 95% Ar + 5% H2 was O246600200008 flowing at 50 ml/min. The gas was subsequently O246600200009 oxidized in passing through a CuO bed. The resulting O246600200010 H2O+HTO gas was absorbed in a molecular sieve. The O246600200011 molecular sieve was periodically changed and eluted O246600200012 with water. O246600200013 DETECTOR (SCIN) The tritiated water was analyzed for the O246600200014 amount of tritium in an automated liquid O246600200015 scintillation system Beckman Instruments LS 6000TA. O246600200016 CORRECTION The measured data were corrected for the H-3 decay O246600200017 and for the neutron background produced in the steel O246600200018 container wall of the Li target. O246600200019 ERR-ANALYS (DATA-ERR) The 7% uncertainty derives from the O246600200020 scatter (5%) of H-3 measurements with two targets and O246600200021 correction for the target wall thickness. O246600200022 STATUS (TABLE) Text (p.16) of FZKA-6764. O246600200023 ENDBIB 21 0 O246600200024 NOCOMMON 0 0 O246600200025 DATA 2 1 O246600200026 DATA DATA-ERR O246600200027 PC/INC PER-CENT O246600200028 2.78 7. O246600200029 ENDDATA 3 0 O246600200030 ENDSUBENT 29 0 O246600299999 SUBENT O2466003 20200408 O078O246600300001 BIB 7 20 O246600300002 REACTION (3-LI-0(D,X)4-BE-7,,PY,,TT) O246600300003 DECAY-DATA (4-BE-7,53.3D,DG,478.,0.1052) O246600300004 METHOD (ACTIV,GSPEC) The Be-7 yield was determined by O246600300005 measuring the 478 keV g-ray line from the irradiated O246600300006 target with a g-ray spectrometer. It was done after a O246600300007 cooling time of about 100 days, but prior to O246600300008 destroying the target for the tritium measurement. O246600300009 DETECTOR (HPGE) The gamma spectrometer was positioned at O246600300010 distance 65 cm from irradiated sample and was O246600300011 protected by a lead collimator in its front to O246600300012 reduce the counting efficiency. Spectrometer was O246600300013 calibrated with Eu-152 g-ray source. O246600300014 CORRECTION The measured data were corrected for decay and for O246600300015 the neutron background produced in the steel target O246600300016 wall, as well as for the gamma ray absorption in the O246600300017 steel wall and in the lithium by about 8%. O246600300018 ERR-ANALYS (DATA-ERR) The 12% uncertainty derives from the O246600300019 scatter of several Be-7 and calibration measurements O246600300020 and the uncertainties of the corrections. O246600300021 STATUS (TABLE) Text (p.18) of FZKA-6764. O246600300022 ENDBIB 20 0 O246600300023 NOCOMMON 0 0 O246600300024 DATA 2 1 O246600300025 DATA DATA-ERR O246600300026 PC/INC PER-CENT O246600300027 0.322 12. O246600300028 ENDDATA 3 0 O246600300029 ENDSUBENT 28 0 O246600399999 ENDENTRY 3 0 O246699999999