Calculation of neutron flux for the intense neutron source (µCF-INS) in optimum conditions

2014 ◽  
Vol 1 (2) ◽  
pp. 39-43
Author(s):  
CHASHTI M.; KALANTARI
Keyword(s):  
Neutron Flux ◽  
Neutron Source ◽  
Optimum Conditions ◽  
Intense Neutron

Pulsed power applications to intense neutron source development

1977 ◽  
Vol 145 (1) ◽  
pp. 179-183 ◽  
Author(s):  
Juan J. Ramirez ◽  
Alan J. Toepfer ◽  
Milton J. Clauser
Keyword(s):  
Neutron Source ◽  
Pulsed Power ◽  
Intense Neutron

A setup with a mechanical chopper for monochromating neutrons and shortening a neutron flux from a pulsed neutron source

2006 ◽  
Vol 49 (5) ◽  
pp. 617-623
Author(s):  
Zh. V. Mezentseva ◽  
A. P. Sirotin ◽  
Yu. V. Grigor’ev ◽  
H. Faikov-Stanczyk
Keyword(s):  
Neutron Flux ◽  
Neutron Source ◽  
Pulsed Neutron ◽  
Pulsed Neutron Source ◽  
Mechanical Chopper

High heat flux target for intense neutron source

1984 ◽  
Vol 55 (1) ◽  
pp. 42-47 ◽  
Author(s):  
F. M. Bacon ◽  
D. F. Cowgill ◽  
C. E. Hickox ◽  
R. J. Walko ◽  
S. R. Subia ◽  
...  
Keyword(s):  
Heat Flux ◽  
Neutron Source ◽  
High Heat ◽  
High Heat Flux ◽  
Intense Neutron

Interferences in instrumental neutron activation analysis by threshold reactions and uranium fission for miniature neutron source reactor

2013 ◽  
Vol 101 (9) ◽  
pp. 601-606
Author(s):  
M. Wasim
Keyword(s):  
Neutron Activation Analysis ◽  
Instrumental Neutron Activation Analysis ◽  
Activation Analysis ◽  
Neutron Activation ◽  
Neutron Flux ◽  
Neutron Source ◽  
Fission Products ◽  
Correction Factors ◽  
Uranium Fission ◽  
Instrumental Neutron Activation

Summary Miniature neutron source reactors (MNSR) are known for their stable neutron flux characteristics and are mostly employed for neutron activation analysis (NAA). Interfering reactions are sometimes observed in instrumental neutron activation analysis (INAA). Failure to correct for these interferences produces significant systematic positive errors. This paper provides correction factors for the interferences caused by the threshold reactions and fission products of 235U. These factors were calculated by using the experimentally determined thermal, epithermal and fast neutron flux and epithermal neutron flux shape factor and the nuclear data from the literature using the Høgdahl convention. Correction factors were calculated for (n, p) and (n, α) reactions for the most commonly observed radionuclides in INAA. Similarly, correction factors for uranium fission were calculated for 9 elements (Ce, Ba, La, Mo, Nd, Pd, Ru, Sm and Zr). The correction factors were validated by analyzing different materials. A comparison of uranium fission factors with those published in the literature showed a good agreement except for 97Zr, 99Mo and 131Ba which is due to difference in the flux characteristics. In general, these factors can be used with confidence.

scholarly journals Radioisotope production at the IFMIF-DONES facility

2020 ◽  
Vol 239 ◽  
pp. 23001
Author(s):  
Javier Praena ◽  
Francisco Garcia-Infantes ◽  
Rafael Rivera ◽  
Laura Fernandez-Maza ◽  
Fernando Arias de Saavedra ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Neutron Source ◽  
Fusion Reactor ◽  
Deuteron Beam ◽  
Nuclear Data ◽  
Important Application ◽  
Medium Size ◽  
Radioisotope Production ◽  
Fusion Technology ◽  
Research Infrastructures

The International Fusion Materials Irradiation Facility - Demo Oriented NEutron Source (IFMIF-DONES) is a single-sited novel Research Infrastructure for testing, validation and qualification of the materials to be used in a fusion reactor. Recently, IFMIF-DONES has been declared of interest by ESFRI (European Strategy Forum on Research Infrastructures) and its European host city would be Granada (Spain). In spite the first and most important application of IFMIF-DONES related to fusion technology, the unprecedented neutron flux available could be exploited without modifying the routine operation of IFMIF-DONES. Thus, it is already planned an experimental hall for a complementary program with neutrons. Also, a complementary program on the use of the deuteron beam could help IFMIF-DONES to be more sustainable. In the present work, we study radioisotope production with deuterons of 177Lu. The results show the viability of IFMIF-DONES for such production in terms of the needs of a territory of small-medium size. Also the study suggests that new nuclear data at higher deuteron energies are mandatory for an accurate study in this field.

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