Development of the Irradiation Facilities for Silicon Neutron Doping in France

1981 ◽  
pp. 287-303 ◽  
Author(s):  
Paul Bréant ◽  
François Cherruau ◽  
Jean-Pierre Genthon
Keyword(s):  
Irradiation Facilities

Design of large sample silicon ingots irradiation facilities using MCNP5

2015 ◽  
Vol 80 ◽  
pp. 40-42 ◽  
Author(s):  
Sarah S. Abdellatief ◽  
Mossa Osman ◽  
Said A. Agamy ◽  
Mohamed E.S. Nagy ◽  
A.A. Elkafas
Keyword(s):  
Large Sample ◽  
Irradiation Facilities

Semi-Empirical LET Descriptions of Heavy Ions Used in the European Component Irradiation Facilities

2010 ◽  
Vol 57 (4) ◽  
pp. 1946-1949 ◽  
Author(s):  
Arto Javanainen ◽  
Wladyslaw Henryk Trzaska ◽  
Reno Harboe-Sørensen ◽  
Ari Virtanen ◽  
Guy Berger ◽  
...  
Keyword(s):  
Heavy Ions ◽  
Semi Empirical ◽  
Irradiation Facilities

137Cs Dosimeter Irradiation Facilities

2017 ◽  
Vol 112 (4) ◽  
pp. 357-363 ◽  
Author(s):  
Andrew J. Boria ◽  
Blake D. Rucinski ◽  
Sara A. Abraham ◽  
Alexander S. Dawson ◽  
Ali H. Jawad ◽  
...  
Keyword(s):  
Irradiation Facilities

Hfir irradiation facilities improvements — the HIFI project

1986 ◽  
Vol 141-143 ◽  
pp. 1018-1024
Author(s):  
G.R. Hicks ◽  
B.H. Montgomery ◽  
K.R. Thoms ◽  
C.D. West
Keyword(s):  
Irradiation Facilities

scholarly journals Experimental and MCNP5 based evaluation of neutron and gamma flux in the irradiation ports of the University of Utah research reactor

2012 ◽  
Vol 27 (3) ◽  
pp. 222-228 ◽  
Author(s):  
Brooklyn Noble ◽  
Dong-Ok Choe ◽  
Tatjana Jevremovic
Keyword(s):  
Reactor Core ◽  
Nickel Wire ◽  
Reactor Model ◽  
University Of Utah ◽  
Training Research ◽  
Gamma Flux ◽  
Dose Measurements ◽  
The University ◽  
Thermo Luminescence ◽  
Irradiation Facilities

Neutron and gamma flux environment of various irradiation ports in the University of Utah training, research, isotope production, general atomics reactor were experimentally assessed and fully modeled using the MCNP5 code. The experimental measurements were based on the cadmium ratio in the irradiation ports of the reactor, flux profiling using nickel wire, and gamma dose measurements using thermo luminescence dosimeter. Full 3-D MCNP5 reactor model was developed to obtain the neutron flux distributions of the entire reactor core and to compare it with the measured flux focusing at the irradiation ports. Integration of all these analysis provided the updated comprehensive neutron-gamma flux maps of the existing irradiation facilities of the University of Utah TRIGA reactor.

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