Three-Dimensional Calculations of Axial Neutron Flux Distribution in a Material Test Research Reactor

2004 ◽  
Vol 4 (2) ◽  
pp. 292-296 ◽  
Author(s):  
S.R. Malkawi
Keyword(s):  
Neutron Flux ◽  
Flux Distribution ◽  
Research Reactor ◽  
Three Dimensional ◽  
Material Test ◽  
Neutron Flux Distribution

Determination of fast neutron flux distribution in irradiation sites of the Malaysian Nuclear Agency research reactor

2011 ◽  
Vol 69 (5) ◽  
pp. 762-767 ◽  
Author(s):  
A.R. Yavar ◽  
S.B. Sarmani ◽  
A.K. Wood ◽  
S.M. Fadzil ◽  
M.H. Radir ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Fast Neutron ◽  
Flux Distribution ◽  
Research Reactor ◽  
Fast Neutron Flux ◽  
Neutron Flux Distribution

scholarly journals CALCULATION OF NEUTRON FLUX DISTRIBUTION AT PIERCING BEAM PORTS OF PLATE TYPE RESEARCH REACTOR BANDUNG

2020 ◽  
Vol 21 (1) ◽  
pp. 25
Author(s):  
Epung Saepul Bahrum ◽  
Prasetyo Basuki ◽  
Alan Maulana ◽  
Jupiter Sitorus Pane
Keyword(s):  
Neutron Flux ◽  
Flux Distribution ◽  
Research Reactor ◽  
Neutron Flux Distribution ◽  
Plate Type

scholarly journals DESIGN OF IRRADIATION FACILITIES AT CENTRAL IRRADIATION POSITION OF PLATE TYPE RESEARCH REACTOR BANDUNG

2020 ◽  
Vol 22 (1) ◽  
pp. 1
Author(s):  
Epung Saepul Bahrum ◽  
Wawan Handiaga ◽  
Yudi Setiadi ◽  
Henky Wibowo ◽  
Prasetyo Basuki ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Thermal Neutron ◽  
Flux Distribution ◽  
Thermal Neutron Flux ◽  
Research Reactor ◽  
Reactor Core ◽  
Irradiation Position ◽  
Neutron Flux Distribution ◽  
Flux Profile ◽  
Plate Type

One of the results from Plate Type Research Reactor Bandung (PTRRB) research program is PTRRB core design. Previous study on PTRRB has not calculated neutron flux distribution at its central irradiation position (CIP). Distribution of neutron flux at CIP is of high importance especially in radioisotope production. In this study, CIP was modeled as a stack of four to five aluminum tubes (AT), each filled by four aluminum irradiation capsules (AIC). Considering AIC dimension and geometry, there are three possibilities of AT configuration. For irradiation sample, 1.45 gr of molybdenum (Mo) was put into AIC. Neutron flux distribution at Mo sample was calculated using TRIGA MCNP and MCNP software. The calculation was simulated at condition when fresh fuel is loaded into reactor core. Analyses of excess reactivity show that, after installing irradiation AT and Mo sample was put into each configuration, the excess reactivity is less than 10.9 %. The highest calculated thermal neutron flux at Mo sample is 5.08×1013 n/cm2.s at configuration 1. Meanwhile, the highest total neutron flux at Mo sample is located at capsule no. II and III. Thermal neutron flux profile is the same for all configurations. This result will be used as a basic data for PTRRB utilization.Keywords: Central Irradiation Position, Neutron Flux Distribution, MCNP, PTRRB

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.

Sign in / Sign up

Export Citation Format

Share Document