2012
DOI: 10.1007/s10967-012-2080-8
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Measurement of thermal neutron capture cross sections of 237Np and 242Pu using prompt gamma neutron activation

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Cited by 12 publications
(2 citation statements)
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“…It is particularly relevant for modeling reactor performance and the development of next generation reactors [1,2] because it has a long half-life of 3.8 × 10 5 years. Little experimental data have been published on the 242 Pu(n,γ) reaction except for a few isolated incident neutron energy regions such as cross section data at thermal energy [3][4][5][6][7][8][9][10] and the energy range of ≈ 6−90 keV [11]. However, an extensive set of the 242 Pu(n,f) cross sections for incident neutron energies ranging from ≈ 10 2 −10 8 eV were reported [12][13][14][15][16][17][18][19][20][21][22][23][24][25][26].…”
Section: Introductionmentioning
confidence: 99%
“…It is particularly relevant for modeling reactor performance and the development of next generation reactors [1,2] because it has a long half-life of 3.8 × 10 5 years. Little experimental data have been published on the 242 Pu(n,γ) reaction except for a few isolated incident neutron energy regions such as cross section data at thermal energy [3][4][5][6][7][8][9][10] and the energy range of ≈ 6−90 keV [11]. However, an extensive set of the 242 Pu(n,f) cross sections for incident neutron energies ranging from ≈ 10 2 −10 8 eV were reported [12][13][14][15][16][17][18][19][20][21][22][23][24][25][26].…”
Section: Introductionmentioning
confidence: 99%
“…References [3][4][5][6][7][8][9][10] report cross sections for thermal neutron capture, and Ref. [11] provides cross sections at incident neutron energies E n ≈ 6-90 keV.…”
Section: Introductionmentioning
confidence: 99%