scholarly journals Comparative of blanket reactor design in assuring of tritium self-sufficiency

2021 ◽  
Vol 2072 (1) ◽  
pp. 012014
Author(s):  
I R Maemunah ◽  
Z Su’ud ◽  
A Waris ◽  
D Irwanto ◽  
P I Yazid
Keyword(s):  
Neutron Flux ◽  
Neutron Irradiation ◽  
Flux Distribution ◽  
Reactor Design ◽  
High Tolerance ◽  
Water Coolant ◽  
Neutron Distribution ◽  
Neutron Flux Distribution ◽  
Self Sufficiency ◽  
Material Component

Abstract The comparison of four blanket modules in DEMO made up the optimization material having a reasonable requirement as blanket material in this study. Either neutron flux distribution in blanket material or material endurance under neutron irradiation, from four modules, the WCLL has a high tolerance neutron distribution and the best neutron irradiation endurance. Furthermore, many suggestions closed to the statement to use the benefits of water coolant and lithium lead (compose Li-6) as a material component in the blanket.

Rechner-Regelung der Neutronenflußverteilung in einem Leistungsreaktor / Computer control of the neutron flux distribution in a power reactor

1974 ◽  
Vol 22 (12) ◽  
Author(s):  
R. Grumbach
Keyword(s):  
Neutron Flux ◽  
Flux Distribution ◽  
Power Reactor ◽  
Computer Control ◽  
Neutron Flux Distribution

Die Neutronenflußverteilung in einem großen Kernreaktor unterliegt Störeinflüssen, deren Auswirkungen durch Regelung beherrscht werden müssen. Zu diesem Zweck wurde ein mit Hilfe eines Prozeßrechners anwendbares Verfahren entwickelt, das ein Regelungsgesetz aus einem Modell des vorhandenen Prozeßzustands errechnet; um zeitraubende physikalische Rechnungen zu vermeiden, werden die benötigten Modellparameter fortlaufend durch empirische Prozeßerkennung ermittelt. In Experimenten mit einem Leistungsreaktor wurde die Anwendbarkeit des Regelungsverfahrens bewiesen.

Determination of thermal neutron flux distribution at the rotary rack served for elemental concentration analysis using the k0-INAA method

2021 ◽  
Vol 10 (1) ◽  
pp. 11-20
Author(s):  
Tho Nguyen Thi ◽  
Anh Tran Tuan ◽  
Cuong Trinh Van ◽  
Doanh Ho Van ◽  
Duong Tran Quoc ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Thermal Neutron ◽  
Flux Distribution ◽  
Thermal Neutron Flux ◽  
Epithermal Neutron ◽  
Epithermal Neutron Flux ◽  
Irradiation Position ◽  
Neutron Flux Distribution ◽  
Sample Irradiation

The accuracy of elements concentration determination using the k0-standardization method directly depends on irradiation and measurement parameters including Non-1/E epithermal neutron flux distribution shape α (ϕ epi ≈1/E1+α ) , thermal-to-epithermal neutron flux ratio f, efficiency ε, peak area… In the case of the irradiation position at the rotary rack of the Dalat Nuclear Research Reactor (DNRR), the difference of thermal neutron flux between the bottom (3.54x1012 n.cm-2.s-1) and the top (1.93x1012 n.cm-2.s-1) of the 15 cm aluminum container is up to 45%. Therefore, it is necessary to accurately determine above-mentioned parameters in the sample irradiation position. The present paper deals with the determination of the distribution of thermal neutron flux along the sample irradiation container by using 0.1% Au–Al wire activation technique. The thermal neutron flux was then used to calculate the concentration of elements in the Standard Reference Material 2711a and SMELS type III using k0-INAA method at different positions in the container. The obtained results with the neutron flux correction were found to be in good agreement with the certified values. In conclusion, the proposed technique can be applied for activation analyses without sandwiching flux monitors between samples during irradiations.

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