scholarly journals Effect of Temperature Difference and Control Rod Movement on Neutron Flux Distribution in Nigeria Research Reactor-1 Core

2017 ◽  
Vol 3 (4) ◽  
Author(s):  
Anas MS
Keyword(s):  
Neutron Flux ◽  
Temperature Difference ◽  
Flux Distribution ◽  
Research Reactor ◽  
Effect Of Temperature ◽  
Control Rod ◽  
Neutron Flux Distribution ◽  
And Control

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 Reactivity Effect Evaluation of Fast Reactor Based on Angular-Dependent Few-Group Cross Sections Generation

Energies ◽  
2021 ◽  
Vol 14 (13) ◽  
pp. 4042
Author(s):  
Xianan Du ◽  
Xuewen Wu ◽  
Youqi Zheng ◽  
Yongping Wang
Keyword(s):  
Neutron Flux ◽  
Angular Dependence ◽  
Cross Sections ◽  
Fast Reactor ◽  
Flux Distribution ◽  
Neutron Transport ◽  
Measurement Data ◽  
Reactivity Effect ◽  
Control Rod ◽  
Neutron Flux Distribution

Among all the possible occurring reactivity effects of a fast reactor, the situations whereby the control rod was inserted, or the coolant was voided could lead to strong anisotropy of neutron flux distribution, therefore the angular dependence on neutron flux should be considered during the few-group cross-sections generation. Therefore, the purpose of this paper is to compare the influence whether the angular dependence on neutron flux is considered in the calculation of few-group cross sections for the reactivity effect calculation. In the study, the 1-D SN finite difference neutron transport equation solver was implemented in the TULIP of SARAX code system so that the high-order neutron flux could be obtained. Meanwhile, the improved Tone’s method was also applied. The numerical results were obtained based on three experimental FR cores, the JOYO MK-I core, ZPPR-9 core, and ZPPR-10B core. Both control rod worth and sodium void reactivity were calculated and compared with the measurement data. By summarizing and comparing the results of 46 cases, significant differences were found between different consideration of the neutronic analysis. The consideration of angular dependence on neutron flux distribution in the few-group cross-sections generation was beneficial to the neutronic design analysis of FR, especially for the reactivity effect calculation.

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

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