ENTRY 14821 20250206 1482100000001 SUBENT 14821001 20250206 20250711 1482100100001 BIB 11 59 1482100100002 TITLE Total neutron cross-section measurement on CH with a 1482100100003 novel 3D-projection scintillator detector 1482100100004 AUTHOR (A.Agarwal,H.Budd,J.Capo,P.Chong,G.Christodoulou, 1482100100005 M.Danilov, A.Dergacheva,A.De Roeck,N.Dokania,D.Douqa, 1482100100006 K.Dugas,S.Fedotov,S.Gwon,R.Howell,K.Iwamoto, 1482100100007 C.Jesus-Valls,C.K.Jung,S.P.Kasetti,M.Khabibullin, 1482100100008 A.Khotjantsev,T.Kikawa,U.Kose,Y.Kudenko,S.Kuribayashi, 1482100100009 T.Kutter,D.Last,L.S.Lin,S.Lin,T.Lux,S.Manly, 1482100100010 D.A.Martinez Caicedo,S.Martynenko, T.Matsubara, 1482100100011 C.Mauger,K.McFarland,C.McGrew,A.Mefodiev,O.Mineev, 1482100100012 T.Nakadaira,E.Noah,A.Olivier,V.Paolone,S.Palestini, 1482100100013 A.Paul-Torres,R.Pellegrino,M.A.Ramirez,C.Riccio, 1482100100014 J.Rodriguez Rondon,F.Sanchez,D.Sgalaberna, 1482100100015 W.Shorrock,A.Sitraka,K.Siyeon,N.Skrobova,S.Suvorov, 1482100100016 A.Teklu,M.Tzanov,Y.Uchida,C.Wret,G.Yang,N.Yershov, 1482100100017 M.Yokoyama,P.Zilberman) 1482100100018 REFERENCE (J,PL/B,840,137843,2023) 1482100100019 #doi:10.1016/j.physletb.2023.137843 1482100100020 INSTITUTE (1USAPEN,1USAROC,2ZZZCER,4RUSLEB,4RUSJIA,1USASTB, 1482100100021 2SWTGVE,1USALSU,3KORCHA,2JPNTOK,2JPNKTO,4RUSMIF, 1482100100022 2JPNKEK,1USAPUP,2SWTETH,2UK IST) 1482100100023 (2SPNSPN) Institut de Fisica d'Altes Energies (IFAE), 1482100100024 The Barcelona Institute of Science and Technology, 1482100100025 Campus UAB, Bellaterra (Barcelona), Spain 1482100100026 (4RUSRUS) Moscow Institute of Physics and Technology 1482100100027 (MIPT), Moscow, Russia 1482100100028 FACILITY (LINAC,1USALAS) The Los Alamos National Laboratory 1482100100029 Weapons Neutron Research (WNR) facility. 1482100100030 DETECTOR (SCIN) 24x8x48 cm3 prototype detector consisting of 1482100100031 9216 1 cm scintillator cubes, exposed to the neutron 1482100100032 beam. Each energy deposit signal in a cube was 1482100100033 collected by three WLS fibers and mapped in three 1482100100034 orthogonal views. The detector used three types of 1482100100035 Hamamatsu MP-PCs, S13360-1325CS, S13081-050CS and 1482100100036 S12571-025C, installed in three different regions of 1482100100037 the top view of the detector. 1482100100038 SAMPLE Plastic scintillator (CH). 1482100100039 METHOD (TRN,TOF) The total neutron cross-section measurement 1482100100040 was estimated utilizing the so-called extinction 1482100100041 technique. In the presence of neutron-nucleus 1482100100042 interactions, the signal event rate decreases 1482100100043 exponentially along the z-coordinate: N(z) = N0*exp(- 1482100100044 T*sigmatot*z), where N0 and N(z) are the neutron 1482100100045 event rates at the reconstructed z positions in the 1482100100046 first layer, and in a more downstream layer in the 1482100100047 detector. T and sigmatot are the nuclear density and 1482100100048 the neutron total cross section, respectively. 1482100100049 ERR-ANALYS (ERR-T) The total uncertainty is dominated by the 1482100100050 contribution from the detection systematic 1482100100051 uncertainty. The detector has a geometrical and 1482100100052 electronics non-uniformity which generates a 1482100100053 detection uncertainty. The fiber, fiber hole, MPPC, 1482100100054 insulating Tyvek layer and cubes have some variation 1482100100055 in their alignment. 1482100100056 (ERR-S) Statistical uncertainty associated with data. 1482100100057 STATUS (TABLE) The data were recovered from the 1482100100058 https://arxiv.org/src/2207.02685v3/anc/. Help 1482100100059 K.Kelly (LANL) with ROOT files is greatly appreciated. 1482100100060 HISTORY (20250206C) BP 1482100100061 ENDBIB 59 0 1482100100062 NOCOMMON 0 0 1482100100063 ENDSUBENT 62 0 1482100199999 SUBENT 14821002 20250206 20250711 1482100200001 BIB 2 3 1482100200002 REACTION (6-C-CMP(N,TOT),,SIG) 1482100200003 STATUS (TABLE,,A.Agarwal+,J,PL/B,840,137843,2023) Table - 1482100200004 Authors data from Fig.7. 1482100200005 ENDBIB 3 0 1482100200006 NOCOMMON 0 0 1482100200007 DATA 4 35 1482100200008 EN DATA ERR-S ERR-T 1482100200009 MEV B B B 1482100200010 99.62600 0.52712 0.01155 0.04645 1482100200011 103.01750 0.52291 0.01162 0.04647 1482100200012 106.59500 0.49983 0.01162 0.04857 1482100200013 110.37300 0.51185 0.01164 0.04907 1482100200014 114.36750 0.47719 0.01166 0.04329 1482100200015 118.59650 0.47777 0.01165 0.05017 1482100200016 123.07900 0.43803 0.01186 0.04570 1482100200017 127.83750 0.45191 0.01183 0.04916 1482100200018 132.89700 0.39088 0.01194 0.04408 1482100200019 138.28400 0.38713 0.01226 0.04455 1482100200020 144.03000 0.40381 0.01205 0.04246 1482100200021 150.17000 0.37421 0.01228 0.04203 1482100200022 156.74250 0.33893 0.01265 0.04179 1482100200023 163.79300 0.37854 0.01234 0.04317 1482100200024 171.37250 0.37018 0.01250 0.04183 1482100200025 179.53900 0.35821 0.01262 0.04966 1482100200026 188.36000 0.34607 0.01261 0.04552 1482100200027 197.91300 0.31464 0.01282 0.04949 1482100200028 208.28950 0.33731 0.01246 0.04837 1482100200029 219.59600 0.34929 0.01229 0.04112 1482100200030 231.95750 0.33391 0.01227 0.04466 1482100200031 245.52300 0.31693 0.01201 0.04451 1482100200032 260.47100 0.32678 0.01164 0.04743 1482100200033 277.01800 0.32921 0.01156 0.04385 1482100200034 295.42750 0.29938 0.01135 0.04054 1482100200035 316.02550 0.33548 0.01094 0.04317 1482100200036 339.22100 0.36914 0.01043 0.04324 1482100200037 365.53100 0.30810 0.01042 0.03997 1482100200038 395.62350 0.35518 0.01034 0.04033 1482100200039 430.37850 0.37047 0.01007 0.04109 1482100200040 470.97850 0.32925 0.00955 0.04255 1482100200041 519.05850 0.34460 0.00838 0.03939 1482100200042 576.95150 0.39534 0.00782 0.04309 1482100200043 648.12050 0.40248 0.00984 0.03890 1482100200044 737.97500 0.51300 0.01801 0.04135 1482100200045 ENDDATA 37 0 1482100200046 ENDSUBENT 45 0 1482100299999 SUBENT 14821003 20250206 20250711 1482100300001 BIB 2 24 1482100300002 SUPPL-INF (INCSP) Neutron energy spectra. 1482100300003 -------------------------------------------------------1482100300004 Incident Normalized Rate (AU) ERR-S (AU) 1482100300005 Neutron 1482100300006 Energy (MeV) 1482100300007 -------------------------------------------------------1482100300008 25.00000 0.02731 0.00066 1482100300009 75.00000 0.13185 0.00145 1482100300010 125.00000 0.15215 0.00156 1482100300011 175.00000 0.13747 0.00148 1482100300012 225.00000 0.11440 0.00135 1482100300013 275.00000 0.09658 0.00124 1482100300014 325.00000 0.08432 0.00116 1482100300015 375.00000 0.07214 0.00107 1482100300016 425.00000 0.05966 0.00097 1482100300017 475.00000 0.05176 0.00091 1482100300018 525.00000 0.05364 0.00092 1482100300019 575.00000 0.05716 0.00095 1482100300020 625.00000 0.05581 0.00094 1482100300021 675.00000 0.03839 0.00078 1482100300022 725.00000 0.01974 0.00056 1482100300023 775.00000 0.00675 0.00033 1482100300024 STATUS (TABLE,,A.Agarwal+,J,PL/B,840,137843,2023) 1482100300025 Authors data from Fig.4. 1482100300026 ENDBIB 24 0 1482100300027 NOCOMMON 0 0 1482100300028 NODATA 0 0 1482100300029 ENDSUBENT 28 0 1482100399999 ENDENTRY 3 0 1482199999999