Validation of neutron flux redistribution factors in JSI TRIGA reactor due to control rod movements

2015 ◽  
Vol 104 ◽  
pp. 34-42 ◽  
Author(s):  
Tanja Kaiba ◽  
Gašper Žerovnik ◽  
Anže Jazbec ◽  
Žiga Štancar ◽  
Loïc Barbot ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Triga Reactor ◽  
Control Rod ◽  
Flux Redistribution

scholarly journals Usage of multiple fission cells for neutron flux measurements during rod-insertion method

2020 ◽  
Vol 225 ◽  
pp. 04024
Author(s):  
Igor Lengar ◽  
Sebastjan Rupnik ◽  
Andrej Žohar ◽  
Vid Merljak ◽  
Marjan Kromar ◽  
...  
Keyword(s):  
Neutron Flux ◽  
Nuclear Power ◽  
Physical Parameters ◽  
Ionization Chambers ◽  
Triga Reactor ◽  
Control Rod ◽  
Multiple Fission ◽  
Insertion Method ◽  
Flux Measurements ◽  
Control Rods

The measurements of physical parameters of the TRIGA reactor and Nuclear power plant Krško (NEK) reactor cores have been in the past performed on hand of the neutron flux signal obtained from uncompensated ionization cells and by employment of the a digital meter of reactivity (DMR). At the TRIGA reactor only one ionization cell is currently used for flux measurements. During the insertion of one control rod the neutron flux distribution is significantly altered affecting the flux measurements of inserting different control rods. The problem is presently solved by assigning a correction factor to each control rod what introduces an additional uncertainty. In the present paper the implementation of four fission cells for reactivity measurements is presented. In this way determining the correct gamma background and its subtraction, performed by DMR algorithms, becomes less important as previously by using ionization chambers. The larger number of detectors also reduces the flux redistribution effects on the signal during individual control rod movements.

scholarly journals Practical, visible wavelength nuclear-pumped laser

1993 ◽  
Vol 11 (3) ◽  
pp. 559-566 ◽  
Author(s):  
Y.R. Shaban ◽  
G.H. Miley
Keyword(s):  
Neutron Flux ◽  
Thermal Neutron ◽  
Thermal Neutron Flux ◽  
Visible Region ◽  
Laser Cavity ◽  
Pumping Power ◽  
University Of Illinois ◽  
Triga Reactor ◽  
Visible Wavelength ◽  
The University

A practical, visible nuclear-pumped laser (NPL) has been sought at the University of Illinois and other laboratories for a number of years. Yet, the results from successful visible NPLs to date have not been fully satisfactory, e.g., the threshold pumping power is too high for conventional applications. Progress in recent studies of 3He-Ne-H2 as a candidate NPL operating in the visible region at 585.3 nm on the 2P1,-1S2 Ne transition is described. We obtained lasing on the above transition for 3He-Ne-H2 concentrations of 1,140, 588, and 412 torr, respectively, with the laser cavity placed in the beamport of the University of Illinois TRIGA reactor. The threshold thermal neutron flux is 1014 n/cm2-s, corresponding to a threshold pumping power of 5 W/cm3.

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.

Physical Design on PMNSR With LEU Core

2017 ◽  
Author(s):  
Wu Xiaobo ◽  
Peng Dan ◽  
Hong Jingyan ◽  
Lu Jin ◽  
Hao Qian
Keyword(s):  
Neutron Flux ◽  
Physical Design ◽  
Second Phase ◽  
Core Element ◽  
Control Rod ◽  
Power Test ◽  
Calculation Results ◽  
Leading Position ◽  
High Enrichment ◽  
Fuel Elements

Prototype Miniature Neutron source Reactor (PMNSR) is a pool-tank type research reactor,applying high enrichment Uranium as fuel, light water as moderator and coolant, beryllium as reflector. Recently, in order to prevent nuclear proliferation, PMNSR carried out low enrichment uranium (LEU) core conversion, and the enrichment of U-235 decreased from 90% to under 20%. Research on PMNSR with LEU core mainly includes theory design, zero power experiment, core replacement. The physical design of PMNSR with LEU is the main part of theory design, which plays a great role in LEU conversion. At the first stage of LEU conversion, it performs preliminary physical calculation and analysis concerning U-235 fuel enrichment, and the number of critical fuel elements, the reactivity worth of control rod, the reactivity worth of top beryllium reflector, the neutron flux of inter-irradiation tube are calculated, which provides important data for the fuel elements design, fabrication, zero power test safety analysis and experiment for LEU conversion. In the second phase, it conducts the result verification on zero power test and preliminary physical design and a preliminary error analysis resulted from it thereof. More over, it modifies input file of LEU conversion, optimizes core element loading deployment, the reactivity worth of central control rod, the neutron flux rate of inner radiation site, offering statistics for the replacement and start-up experiments. In the last period, grounded on the counting abnormal analysis in loading, it explains the reasons with calculation results, completing PMNSR LEU conversion. PMNSR physical design takes the leading position in LEU conversion. It supplies reference data to ensure completion of PMNSR conversion and lays a theoretical foundation for Ghana and Nigeria MNSR LEU core conversion.

Neutron flux measurements at the TRIGA reactor in Vienna for the prediction of the activation of the biological shield

2011 ◽  
Vol 69 (11) ◽  
pp. 1621-1624 ◽  
Author(s):  
Stefan Merz ◽  
Mile Djuricic ◽  
Mario Villa ◽  
Helmuth Böck ◽  
Georg Steinhauser
Keyword(s):  
Neutron Flux ◽  
Triga Reactor ◽  
Flux Measurements
Sign in / Sign up

Export Citation Format

Share Document