Thermal Flux Distribution from a Fast Neutron Line Source

1956 ◽  
Vol 27 (1) ◽  
pp. 89-90
Author(s):  
G. W. Stuart
Keyword(s):  
Fast Neutron ◽  
Line Source ◽  
Flux Distribution ◽  
Thermal Flux

Performance of a 100 kWth Concentrated Solar Beam-Down Optical Experiment

2014 ◽  
Vol 136 (4) ◽  
Author(s):  
Marwan Mokhtar ◽  
Steven A. Meyers ◽  
Peter R. Armstrong ◽  
Matteo Chiesa
Keyword(s):  
Flux Distribution ◽  
Thermal Flux ◽  
Heat Transfer Fluid ◽  
Distribution Data ◽  
Fluid Temperature ◽  
Aperture Size ◽  
Optical Efficiency ◽  
Optimal Receiver ◽  
Daily Average ◽  
Optical Experiment

An analysis of the beam down optical experiment (BDOE) performance with full concentration is presented. The analysis is based on radiation flux distribution data taken on Mar. 21st, 2011 using an optical-thermal flux measurement system. A hypothetical thermal receiver design is used in conjunction with the experimental data to determine the optimal receiver aperture size as a function of receiver losses and flux distribution. The overall output of the plant is calculated for various operating temperatures and three different control strategies namely, constant mass flow of the heat transfer fluid (HTF), constant outlet fluid temperature and real-time optimal outlet fluid temperature. It was found that the optimal receiver aperture size (radius) of the receiver ranged between (1.06 and 1.71 m) depending on temperature. The optical efficiency of the BDOE ranged from 32% to 37% as a daily average (average over the ten sunshine hours). The daily average mean flux density ranged between 9.422 kW/m2 for the 1.71 m-receiver and 20.9 kW/m2 for the 1.06 m-receiver. Depending on the control parameters and assuming an open receiver with solar absorptivity of 0.95 and longwave emissivity of 0.10. The average receiver efficiency varied from 71% at 300 °C down to 68% at 600 °C. The overall daily average thermal efficiency of the plant was between 28% and 24%, respectively for the aforementioned temperatures. The peak of useful power collected in the HTF was around 105 kWth at 300 °C mean fluid temperature and 89 kWth at 600 °C.

The fast neutron energy spectrum and the thermal neutron flux distribution in the experimental channel of the VVR reactor

Atomic Energy ◽  
1962 ◽  
Vol 12 (2) ◽  
pp. 127-132 ◽  
Author(s):  
N. V. Zvonov ◽  
A. I. Mis'kevich ◽  
I. V. Rogozhkin ◽  
V. I. Tereshchenko ◽  
Zh. I. Turkov ◽  
...  
Keyword(s):  
Energy Spectrum ◽  
Neutron Flux ◽  
Thermal Neutron ◽  
Fast Neutron ◽  
Neutron Energy ◽  
Flux Distribution ◽  
Thermal Neutron Flux ◽  
Neutron Energy Spectrum ◽  
Experimental Channel ◽  
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 The effect of control rods on the reactivity and flux distribution of BWR 4 bundle using MCNPX Code

2021 ◽  
Vol 11 (1) ◽  
Author(s):  
Sayed. Saeed. Mustafa
Keyword(s):  
Neutron Flux ◽  
Flux Distribution ◽  
Parametric Design ◽  
Thermal Flux ◽  
Boiling Water ◽  
Boiling Water Reactor ◽  
Time Step ◽  
Water Reactor ◽  
Mcnpx Code ◽  
Safety Considerations

AbstractThis paper has three main objectives related to the neutronic and burnup analysis of the BWR (Boiling Water Reactor) Four-Lattice. The first objective is to provide partial validation of the MCNPX code for this lattice by comparing its results with Scale-5.1 results. Validation of the MCNPX to calculate effective multiplication factor and reactivity rod worth for the F-Lattice is provided. This is carried out in case of instantly removing the control blade and replacing it with a graphite moderator. Moreover, spatial neutron flux distributions using F-mesh card over the bundle and the control blade are investigated at inserting and withdrawing the B4C. The second objective is to perform parametric design studies of the F-Lattice. Areas of particular interest are the effect of increased or decreased blade width on the neutron flux throughout the bundle. It is found that the presence of carbon in the control blade at withdrawing the B4C makes the reactor supercritical, (K-eff = 1.22206). On the other hand, the use of B4C blade presents (K-eff = 0.93521). Consequently, the reactivity of 10% B4C thinner case is higher that of 10% B4C thicker. The simulation also showed that the B4C blade had an effective role in decreasing the thermal flux at the periphery of the bundle. This is contrast to the effect of carbon that moderates fast to thermal neutrons. The third part of this work aims at studying the burnup calculations using MCNPX code for 30 days burn with 1 day time step then for 20 months burn with 2 week time steps for the lattice. At the end of the work, it is very important to determine the most proper bundle model that achieves a prolonged fuel burn and flatting thermal flux distribution. For reaching this goal, three cases (B4C, 10% thinner of B4C and 10% thicker) are simulated by MCNPX code till 70 GWd/ton. It is found that the B4C and 10% thicker are the appropriate models that can satisfy the safety considerations of the Compact Modular Boiling Water Reactor.

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