scholarly journals Optimization of the testing volumes with respect to neutron flux levels in the two-target high flux D-Li neutron source for the international fusion materials irradiation facility

2003 ◽  
Author(s):  
W.P. Kelleher ◽  
G.L. Versamis
Keyword(s):  
Neutron Flux ◽  
Neutron Source ◽  
High Flux ◽  
Fusion Materials

High-flux neutron source based on a liquid-lithium target

2013 ◽  
Author(s):  
S. Halfon ◽  
G. Feinberg ◽  
M. Paul ◽  
A. Arenshtam ◽  
D. Berkovits ◽  
...  
Keyword(s):  
Neutron Source ◽  
Liquid Lithium ◽  
High Flux ◽  
Lithium Target

scholarly journals The Contribution of Peripheral Large Scientific Infrastructures to Sustainable Development from a Global and Territorial Perspective: The Case of IFMIF-DONES

2021 ◽  
Vol 13 (2) ◽  
pp. 454
Author(s):  
Virginia Fernández-Pérez ◽  
Antonio Peña-García
Keyword(s):  
Sustainable Development ◽  
Social Development ◽  
Economic Impact ◽  
Neutron Source ◽  
Major Focus ◽  
Fusion Materials ◽  
Indirect Impact ◽  
Global Contribution

Large scientific infrastructures are a major focus of progress. They have a big impact on the economic and social development of their surroundings. Departing from these well-known facts, it is not trivial to affirm whether the global contribution to Sustainable Development (SD) is higher when they are built in peripheral and not highly developed provinces instead of capitals and rich areas. Besides the economic impact on depressed areas, other SD-related parameters like the attachment of young and skilled people to their homeland, the avoidance of uncontrolled migrations from rural to dense urban zones, the growth of new focuses of knowledge independent from the lines of research established in the universities of the capitals, the indirect impact of auxiliary infrastructures and others must be analyzed. Concerning the next implementation of the “International Fusion Materials Irradiation Facility—Demo Oriented Neutron Source” (IFMIF-DONES) project in Granada (Spain), one depressed and tourism-dependent zone, an analysis and comparison with similar infrastructures were done and presented.

scholarly journals High-performance deuterium-lithium neutron source for fusion materials and technology testing

2003 ◽  
Author(s):  
G.P. Lawrence ◽  
T.S. Bhatia ◽  
B. Blind ◽  
F.W. Guy ◽  
R.A. Krakowski ◽  
...  
Keyword(s):  
Neutron Source ◽  
High Performance ◽  
Fusion Materials

scholarly journals Viability of the ESS-Bilbao neutron source for irradiation of nuclear fusion materials

2014 ◽  
Vol 444 (1-3) ◽  
pp. 469-474 ◽  
Author(s):  
A.R. Páramo ◽  
F. Sordo ◽  
J.M. Perlado ◽  
A. Rivera
Keyword(s):  
Neutron Source ◽  
Nuclear Fusion ◽  
Fusion Materials

scholarly journals Reducing risk and accelerating delivery of a neutron source for fusion materials research

2014 ◽  
Vol 89 (4) ◽  
pp. 273-279 ◽  
Author(s):  
E. Surrey ◽  
M. Porton ◽  
T. Davenne ◽  
D. Findlay ◽  
A. Letchford ◽  
...  
Keyword(s):  
Neutron Source ◽  
Fusion Materials ◽  
Materials Research

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

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.

Radiotoxicity of Actinides During Transmutation in Final Stage of Atomic Power

2002 ◽  
Author(s):  
Aleksander S. Gerasimov ◽  
Boris R. Bergelson ◽  
Lidia A. Myrtsymova ◽  
Georgy V. Tikhomirov
Keyword(s):  
Neutron Flux ◽  
Flux Density ◽  
Final Stage ◽  
High Flux ◽  
Neutron Flux Density

Characteristics of a transmutation mode in final stage of atomic power are analyzed. In this stage, transmutation of actinides accumulated in transmutation reactors is performed without feed by actinides from other reactors. The radiotoxicity during first 20 years of transmutation is caused mainly by 244Cm. During following period of time, 252Cf is main nuclide. Contribution of 246Cm and 250Cf is 5–7 times less than that of 252Cf. During 50 years of a transmutation, the total radiotoxicity falls by 50 times. Long-lived radiotoxicity decreases slowly. During the period between T = 50 years and T = 100 years, long-lived radiotoxicity falls by 3.7 times. For each following 50 years after this period, long-lived radiotoxicity falls by 3.2 times. These results corresponding to neutron flux density 1014 neutr/(cm2s) in transmutation reactor demonstrate that the final stage of a transmutation should be performed with use of high flux transmutation facilities which provide shorter time of transmutation.

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.

Measurement of neutron fluence in the High-Flux Test Module of the Early Neutron Source by neutron activation

2019 ◽  
Vol 146 ◽  
pp. 1258-1261
Author(s):  
Axel Klix ◽  
Frederik Arbeiter ◽  
Mitja Majerle ◽  
Yuefeng Qiu ◽  
Milan Štefánik
Keyword(s):  
Neutron Activation ◽  
Neutron Source ◽  
Neutron Fluence ◽  
High Flux ◽  
Test Module
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