Measurements of neutron total and capture cross sections of ²⁴¹Am with ANNRI at J-PARC

References

• Iwamoto H, Nishihara K, Sugawara T, et al. Sensitivity and uncertainty analysis for an accelerator-driven system with JENDL-4.0. J Nucl Sci Technol. 2013;50:856–862.
   Web of Science ®Google Scholar
• Shibata K, Iwamoto O, Nakagawa T, et al. JENDL-4.0: a new library for nuclear science and technology. J Nucl Sci Technol. 2011;48:1–30.
   Web of Science ®Google Scholar
• Salvatore M, Jacqmin R Uncertainty and target accuracy assessment for innovative systems using recent covariance data evaluations. WPEC-26, OECD NEA (2008).
   Google Scholar
• JENDL-4.0 data file for ²⁴¹Am (MAT=9543), evaluated by Iwamoto N (2010).
   Google Scholar
• Harada H, Iwamoto O, Iwamoto N, et al. Accuracy improvement of neutron nuclear data on minor actinides. In Proceedings of the 15ʹth International Symposium on Capture Gamma-Ray Spectroscopy and Related Topics (CGS 15); 2014 August 25–29; Dresden, Germany. EPJ Web of Conferences 93.
   Google Scholar
• Harada H, Iwamoto O, Iwamoto N, et al. Research and development for accuracy improvement of neutron nuclear data on minor actinides. In Proceedings of the International Conference on Nuclear Data for Science and Technology (ND2016); 2016 September 11–16; Bruges, Belgium. EPJ Web of Conferences 2017;146:11001.
   Google Scholar
• Nakao T, Terada K, Kimura A, et al. Developments of a new data acquisition system at ANNRI. In Proceedings of the International Conference on Nuclear Data for Science and Technology (ND2016); 2016 September 11–16; Bruges, Belgium. EPJ Web of Conferences 2017;146:03021.
   Google Scholar
• Terada K, Nakao T, Kimura A, et al. Technical developments for accurate determination of amount of samples used for TOF measurements. In Proceedings of the International Conference on Nuclear Data for Science and Technology (ND2016); 2016 September 11–16; Bruges, Belgium. EPJ Web of Conferences 2017;146:03019.
   Google Scholar
• Hirose K, Furutaka K, Hara K, et al. Cross-section measurement of 237Np(n,γ) from 10 meV to 1 keV at Japan proton accelerator research complex. J Nucl Sci Technol. 2013;50:188–200.
   Web of Science ®Google Scholar
• Harada H, Ohta M, Kimura A, et al. Measurements of 241Am(n, γ) at J-PARC/MLF/ANNRI. Nuclear Data Sheets. 2014;119:61–64.
   Web of Science ®Google Scholar
• Kimura A, Fujii T, Fukutani S, et al. Neutron-capture cross-sections of 244Cm and 246Cm measured with an array of large germanium detectors in the ANNRI at J-PARC/MLF. J Nucl Sci Technol. 2011;49:708–724.
   Web of Science ®Google Scholar
• Mendoza E, Cano-Ott D, Guerrero C, et al. Measurement and analysis of the 243Am neutron capture cross section at the n_TOF facility at CERN. Phys Rev C. 2014;90:034608.
   Web of Science ®Google Scholar
• Adamchuk JV, Gerasimov VF, Efimov BV, et al. The fission and total cross-sections measurement for heavy elements isotopes by monochromatic neutrons using mechanical selector. In Proceedings of the International Conference on Peaceful Uses of Atomic Energy; 1955 August 8; Geneva, Schweizerische. Vol.4, p.259.
   Google Scholar
• Slaughter GG, Block RC, Harvey JA. High-resolution total cross section measurements on 237Np and 241Am using the ORNL fast chopper. Am Phys Soc. 1961;6:70.
   Google Scholar
• Derrien H, Lucas B The total cross section and the fission cross section of 241Am in the resonance region. In Proceedings of the International Conference on nuclear cross sections and technology; 1975 March 3–7; Washington, D.C., USA. Vol. 2, p. 637.
   Google Scholar
• Belanova TS, Kolesov AG, Nikolaev VM, et al. Parameters of the neutron resonances of 241Am in the energy range from 8 to 30 eV. Sov At Energy. 1975;38:29.
   Web of Science ®Google Scholar
• Kalabin SM, Artamonov VS, Ivanov RN, et al. Total neutron cross section and neutron resonance parameters of 241Am in the energy range 0.004–30 eV. Sov At Energy. 1976;40:303.
   Web of Science ®Google Scholar
• Phillips TW, Howe RE. Total neutron cross section for Americium-241. Nucl Sci Eng. 1979;69:375–377.
   Web of Science ®Google Scholar
• Lampoudis C, Kopecky S, Bouland O, et al. Neutron transmission and capture cross section measurements for 241Am at the GELINA facility. Eur Phys J Plus. 2013;128:86.
   Web of Science ®Google Scholar
• Shibata K, Kawano T, Nakagawa T, et al. Japanese evaluated nuclear data library version 3 revision-3: JENDL-3.3. J Nucl Sci Technol. 2002;39:1125–1136.
   Web of Science ®Google Scholar
• Pomerance H. Absorption cross sections for long-lived fission-product Zr93, Am241, and enriched stable platinum isotopes, in Physics Division Semiannual Progress Report (ORNL). 1955; 5055.
   Google Scholar
• Bak MA, Krivokhatskii AS, Petrzhak KA, et al. Cross sections and resonance integrals for capture and fission in long-lived americium isotopes. Atomnaya Energiya. 1967;23:316.
   Google Scholar
• Dovbenko AG, Ivanov VI, Kolesov VE, et al. Am-241 radiative neutron capture. Centr Po Jadernym Dannym, Obninsk. 1969;6:42.
   Google Scholar
• Harbour RM, Mac Murdo KW, Crosson FJ. Thermal-neutron capture cross sections and capture resonance integrals of Americium-241. Nucl Sci Eng. 1973;50:364.
   Web of Science ®Google Scholar
• Gavrilov VD, Goncharov VA, Ivaneko VV, et al. Thermal cross sections and resonance integrals of fission and capture of Am-241, Am-243, Bk-249, and Cf-249. Atomnaya Energiya. 1976;41:808.
   Google Scholar
• Shinohara N, Hatsukawa Y, Hata K, et al. Radiochemical determination of neutron capture cross section of 241Am. J Nucl Sci Technol. 1997;34:613–621.
   Web of Science ®Google Scholar
• Fioni G, Cribier M, Marie F, et al. Incineration of 241Am induced by thermal neutrons. Nucl Phys. 2001;693:546–564.
   Web of Science ®Google Scholar
• Maidana NL, Dias MS, Foskinas MF. Measurement of the thermal neutron capture cross section and resonance integral of Am-241. Radiochimica Acta. 2001;89:419–423.
   Web of Science ®Google Scholar
• Bringer O, AlMahamid I, Chabod S, et al. Measurements of thermal fission and capture cross sections of minor actinides within the Mini-INCA project. In Proceedings of the International Conference onNuclear Data for Science and Technology 2007; 2007 April 22–28; Nice, France. p. 619–622.
   Google Scholar
• Nakamura S, Ohta S, Harada H, et al. Thermal-neutron capture cross section and resonance integral of Americium-241. J Nucl Sci Technol. 2007;44:1500–1508.
   Web of Science ®Google Scholar
• Jandel M, Bredeweg TA, Bond EM, et al. Neutron capture cross section of 241Am. Phys Rev C. 2008;78:034609.
   Web of Science ®Google Scholar
• Belgya T, Szentmiklosi L, Kis Z, et al. Measurement of 241Am ground state radiative neutron capture cross section with cold neutron beam. IAEA Report INDC (HUN). 2012;0037.
   Google Scholar
• Genreith C, Rossbach M, Révay Z, et al. Determination of (n,γ) cross sections of 241Am by cold neutron activation. Nuclear Data Sheets. 2014;119:69–71.
   Web of Science ®Google Scholar
• Lampoudis C, Kopecky S, Bouland O, et al. Neutron transmission and capture cross section measurements for 241Am at the GELINA facility. Eur Phys J Plus. 2013;128:86.
   Web of Science ®Google Scholar
• Fraval K, Gunsing F, Altstadt S, et al. Measurement and analysis of the 241Am(n,γ) cross section with liquid scintillator detectors using time-of-flight spectroscopy at the n_TOF facility at CERN. Phys Rev C. 2014;89:044609.
   Web of Science ®Google Scholar
• Hirose K, Nishio K, Makii H, et al. Simultaneous measurement of neutron-induced fission and capture cross sections for 241Am at neutron energies below fission threshold. Nucl Instruments Methods Phys Res Section. 2017;856:133–138.
   Web of Science ®Google Scholar
• Žerovnik G, Schillebeeckx P, Cano-Ott D, et al. Improving nuclear data accuracy of 241Am and 237Np capture cross sections. In Proceedings of the International Conference on Nuclear Data for Science and Technology (ND2016); 2016 September 11–16; Bruges, Belgium. EPJ Web of Conferences 2017; 146:11035.
   Google Scholar
• Maekawa F, Harada M, Oikawa K, et al. First neutron production utilizing J-PARC pulsed spallation neutron source JSNS and neutronic performance demonstrated. Nucl Instruments Methods Phys Res Section. 2010;2010(620):159165.
   Google Scholar
• Shibahara S, Hori J, Takamiya K, et al. High precision analysis of isotopic composition for samples used for nuclear cross-section measurements. In Proceedings of the International Conference on Nuclear Data for Science and Technology (ND2016); 2016 September 11–16; Bruges, Belgium. EPJ Web of Conferences 2017; 146:03028.
   Google Scholar
• Igashira M, Kiyanagi Y, Oshima M. Nuclear data study at J-PARC BL04. Nucl Instruments Methods Phys Res Section. 2009;600:332–334.
   Web of Science ®Google Scholar
• Kino K, Furusaka M, Hiraga F, et al. Measurement of energy spectra and spatial distributions of neutron beams provided by the ANNRI beamline for capture cross-section measurements at the J-PARC/MLF. Nucl Instruments Methods Phys Res Section. 2011;626:58–66.
   Web of Science ®Google Scholar
• Syme DM. The black and white filter method for background determination in neutron time-of-flight spectrometry. Nuclear Instruments Methods. 1982;198:364– 365.
   Google Scholar
• JEFF-3.2 data file for ²⁴¹Am (MAT=9543), evaluated by CEA/NRG/IRMM collaboration (2014).
   Google Scholar
• ENDF/B-VII.1 data file for ²⁴¹Am (MAT=9543), evaluated by Kawano T and Chadwick M B (2011).
   Google Scholar
• Kimura A, Fujii T, Fukutani S, et al. Neutron-capture cross-sections of 244Cm and 246Cm measured with an array of large germanium detectors in the ANNRI at J-PARC/MLF. J Nucl Sci Technol. 2012;49:708–724.
   Web of Science ®Google Scholar
• Kin T, Furutaka K, Goko S, et al. Development of a 4-pi germanium spectrometer for nuclear data measurements at J-PARC. In Proceedings of the International Conference on 2009 IEEE Nuclear Science Symposium and Medical Imaging; 2009 October 25–31, Orland, USA. pp. 2531.
   Google Scholar
• Macklin RL, Gibbons JH. Capture-cross-section studies for 30–220 keV neutrons using a new technique. Phys Rev. 1967;159:1007–1015.
   Web of Science ®Google Scholar
• JENDL-4.0 data file for ¹⁰B (MAT = 525), evaluated by Chiba S (2010).
   Google Scholar
• Sato T, Niita K, Matsuda N, et al. Particle and heavy ion transport code system PHITS version 2.52. J Nucl Sci Technol. 2013;50:913–923.
   Web of Science ®Google Scholar
• JENDL-4.0 data file for ¹⁹⁷Au (MAT=7925), evaluated by Iwamoto N (2010).
   Google Scholar
• Allison J, Amako K, Apostolakis J, et al. Recent developments in Geant4. Nucl Instruments Methods Phys Res Section. 2016;835:186–225.
   Web of Science ®Google Scholar
• Verbeke JM, Hagmann C, Wright D. Simulation of neutron and gamma ray emission from fission and photofission. UCRL-AR-228518-REV-1, Lawrence Livermore National Laboratory; 2016.
   Google Scholar
• Carlson AD, Pronyaev VG, Smith DL, et al. International evaluation of neutron cross section standards. Nuclear Data Sheets. 2009;110:3125–3324.
   Web of Science ®Google Scholar
• Mizuyama K, Iwamoto N, Iwamoto O. Correction of the thermal neutron capture cross section of 241Am obtained by the Westcott convention. J Nucl Sci Technol. 2017;54:74–80.
   Web of Science ®Google Scholar