scholarly journals 245CM FISSION CROSS SECTION MEASUREMENT IN THE THERMAL ENERGY REGION

2010 ◽  
Author(s):  
O. SEROT ◽  
C. WAGEMANS ◽  
S. VERMOTE ◽  
J. VAN GILS
Keyword(s):  
Cross Section ◽  
Thermal Energy ◽  
Energy Region ◽  
Fission Cross Section ◽  
Cross Section Measurement ◽  
Section Measurement

Fission cross section measurement on 233U

1970 ◽  
Vol 24 (3) ◽  
pp. 111-121 ◽  
Author(s):  
M.G. Cao ◽  
E. Migneco ◽  
J.P. Theobald ◽  
M. Merla
Keyword(s):  
Cross Section ◽  
Fission Cross Section ◽  
Cross Section Measurement ◽  
Section Measurement

scholarly journals Neutron-induced fission cross-section measurement of 234U with monoenergetic beams in the keV and MeV range using MicroMegas detectors

2019 ◽  
Vol 24 ◽  
pp. 250
Author(s):  
A. Kanellakopoulos ◽  
A. Stamatopoulos ◽  
A. Tsinganis ◽  
M. Kokkoris ◽  
R. Vlastou ◽  
...  
Keyword(s):  
Cross Section ◽  
Neutron Beam ◽  
Cross Sections ◽  
Fission Cross Section ◽  
Incident Neutron ◽  
Tandem Accelerator ◽  
Cross Section Measurement ◽  
Preliminary Results ◽  
Section Measurement ◽  
Induced Fission

The fission cross-section of 234U was measured at incident neutron energies between 300 and 500 keV and 4 and 5 MeV with a setup based on “microbulk” MicroMegas detectors. The standard 235,238U fission cross-sections were used as reference. The neutron beams were produced via the 7Li(p,n) and the 2H(d,n) reactions at the neutron beam facility of the 5.5 MeV Tandem accelerator laboratory at NCSR “Demokritos”. The mass of the actinide content of the targets used and of their impurities was quantitatively determined via α – spectroscopy. The developed methodology and preliminary results are presented.

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