Cross Section Measurements in the 235U Fission Spectrum Neutron Field

1985 ◽  
pp. 867-875 ◽  
Author(s):  
D. M. Gilliam ◽  
J. A. Grundl ◽  
G. P. Lamaze ◽  
E. D. McGarry ◽  
A. Fabry
Keyword(s):  
Cross Section ◽  
Neutron Field ◽  
Fission Spectrum ◽  
235U Fission

Cross Section Measurements in the 235U Fission Spectrum Neutron Field

1985 ◽  
pp. 867-875
Author(s):  
D. M. Gilliam ◽  
J. A. Grundl ◽  
G. P. Lamaze ◽  
E. D. McGarry ◽  
A. Fabry
Keyword(s):  
Cross Section ◽  
Neutron Field ◽  
Fission Spectrum ◽  
235U Fission

Testing of Scintillation Detectors in Quasi-Monoenergetic Neutron Spectra in a Silicon Filtered Neutron Beam at the LVR-15 Research Reactor

2019 ◽  
Vol 5 (3) ◽  
Author(s):  
Michal Košťál ◽  
Zdeněk Matěj ◽  
Filip Mravec ◽  
František Cvachovec ◽  
Martin Schulc ◽  
...  
Keyword(s):  
Cross Section ◽  
Homeland Security ◽  
Pulse Shape ◽  
Spontaneous Fission ◽  
Research Reactor ◽  
Neutron Field ◽  
Pulse Shape Discrimination ◽  
Shape Discrimination ◽  
Neutron Spectra ◽  
Fission Spectrum

With increasing needs of neutron detection in energy and homeland security sectors, there is an aim in the development of new suitable detection materials with possible n/g separation and also satisfactory resolution. This issue is connected with a well-defined neutron field. The neutron standards 252Cf(spontaneous fission) and 235U(nth fission) have smooth spectra; thus, the tests in these fields can be used for testing of neutron gamma pulse shape discrimination (PSD), but cannot reveal possible problems in the deconvolution. New neutron field which is formed from fission spectrum filtered by 1 m thick silicon block was developed in Research Center Rez. Due to the course of the silicon cross section, the well-distinguished neutron peaks occur in filtered neutron spectrum. In this field, various scintillation materials, HIDEX Aqualight, and EJ299-33A were tested.

Fission spectrum averaged cross-section of 94Zr(n, α)91Sr

1980 ◽  
Vol 7 (2) ◽  
pp. 73-77 ◽  
Author(s):  
O. Horibe ◽  
Y. Mizumoto
Keyword(s):  
Cross Section ◽  
Fission Spectrum

Fission spectrum averaged cross section measurements of some neutron threshold reactions of relevance to medical radionuclide production

2005 ◽  
Vol 93 (9-10) ◽  
Author(s):  
Jamshed H. Zaidi ◽  
M. Arif ◽  
I. Fatima ◽  
Shahida Waheed ◽  
Shujaat Ahmad ◽  
...  
Keyword(s):  
Nuclear Reaction ◽  
Cross Section ◽  
Cross Sections ◽  
Fission Neutron ◽  
Reaction Cross ◽  
Radionuclide Production ◽  
Fission Neutron Spectrum ◽  
Fission Spectrum ◽  
Medical Radionuclide ◽  
Reaction Cross Sections

SummaryA resume is given of radiochemical measurements of nuclear reaction cross sections relevant to the production of some medically important radionuclides carried out at PINSTECH during the last decade. Systematic studies on fission neutron spectrum averaged cross sections of several threshold reactions, like (

scholarly journals Fast neutron spectrum unfolding of a TRIGA Mark II reactor and measurement of spectrum-averaged cross sections: integral tests of differential cross sections of neutron threshold reactions

2013 ◽  
Vol 101 (10) ◽  
pp. 613-620 ◽  
Author(s):  
M. S. Uddin ◽  
S. Sudár ◽  
S. M. Hossain ◽  
R. Khan ◽  
M. A. Zulquarnain ◽  
...  
Keyword(s):  
Fast Neutron ◽  
Cross Sections ◽  
Nuclear Reactions ◽  
Neutron Field ◽  
Fast Neutrons ◽  
Metal Foils ◽  
Spectrum Unfolding ◽  
Fission Spectrum ◽  
Data Files ◽  
Triga Mark Ii

Summary The spectrum of fast neutrons having energies from 0.5 to 20 MeV in the core of the 3MW TRIGA Mark II reactor at Savar, Dhaka, Bangladesh, was unfolded by activating several metal foils to induce threshold nuclear reactions covering the whole spectrum, and then doing necessary iterative calculations utilizing the activation results and the code SULSA. The analysed shape of the spectrum in the TRIGA core was found to be similar to that of the pure 235U-fission spectrum, except for the energies between 0.5 and 1.5 MeV, where it was slightly higher than the fission spectrum. Spectrum-averaged cross sections were determined by integral measurements. The integral values measured in this work were compared with the recommended values for a pure fission spectrum as well as with the integrated data deduced from measured and evaluated excitation functions of a few reactions given in some data files. The good agreement between integral measurements and integrated data in case of well-investigated reactions shows that the fast neutron field at the TRIGA Mark II reactor can be used for validation of evaluated data of neutron threshold reactions.

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