scholarly journals Dosimetry Issues for an Ultra-High Flux Beam and Multipurpose Research Reactor Design

2009 ◽  
pp. 568-568-10
Author(s):  
CD West
Keyword(s):  
Research Reactor ◽  
Reactor Design ◽  
High Flux

scholarly journals HIGH FLUX RESEARCH REACTOR (HFRR). Reactor Design and Feasibility Study

1956 ◽  
Author(s):  
R. D. Cheverton ◽  
A. W. Charmatz ◽  
R. L. Crowther ◽  
R. J. Feinberg ◽  
G. A. Maortensen ◽  
...  
Keyword(s):  
Feasibility Study ◽  
Research Reactor ◽  
Reactor Design ◽  
High Flux

scholarly journals Calculations of research reactor thermal hydraulics based on VVER-440 fuel assamblies

2019 ◽  
Vol 5 (4) ◽  
pp. 317-321
Author(s):  
Thi Zieu Chang Doan ◽  
Georgy E. Lazarenko ◽  
Denis G. Lazarenko
Keyword(s):  
Flow Regime ◽  
Research Reactor ◽  
Reactor Design ◽  
Coolant Flow ◽  
Normal Operation ◽  
Coolant Temperature ◽  
Saturation Curve ◽  
Thermal Hydraulics ◽  
Pressurized Water ◽  
Wide Range

Having thoroughly analyzed the design features of VVER-type pressurized water reactors and VVR-type research reactors, the authors propose a design of a research reactor with low-enriched fuel based on deeply updated VVER-440 fuel assemblies. The research reactor is intended to solve a wide range of applied problems in nuclear physics, radiation chemistry, materials science, biology, and medicine. The calculated thermal hydraulics confirms the correctness of the fundamental approaches laid down in the reactor design. An equivalent reactor core model in the form of a thick-walled cylinder was considered, and the radial power density distribution was obtained. According to the heat power level, five groups of FAs were identified. For each group, the coolant mass flow rate was calculated, which ensures alignment with the outlet coolant temperature. The coolant flow regime was also estimated. It turned out that for the first row of FAs, the flow regime is in the transition region, while for the other rows the flow regime is laminar. A test by the Gr.Pr≥1.105 criterion showed its conformity (the calculated value was 1.96.106), indicating the transition to a viscous-gravitational regime. The FE surface overheating was calculated relative to the mixed coolant average temperature. The axial coolant flow temperature distribution is the same in all the FAs, the change in power is compensated by the corresponding change in the coolant flow. The maximum coolant overheating on the FE wall relative to the flow core is observed in the central FAs, reaching 31 °C, the boiling margin is about 15 °C. The estimates showed a significant dynamic pressure margin during natural thermal-convective circulation. By calculation, the values of the FE surface overheating during the reactor normal operation were obtained. An approximately 15-degree surface overheating margin relative to the saturation curve is shown, which guarantees the absence of cavitation wear of the FE claddings. In general, the performed calculations confirmed the correctness of the approaches laid down in the reactor design and made it possible to specify the core thermal hydraulics necessary for further developing the concept.

scholarly journals University of Missouri Research Reactor LEU Fuel Element Flow Test Conceptual Design – Hydraulic Reactor Design Parameters

2021 ◽  
Author(s):  
Guanyi Wang ◽  
Cezary Bojanowski ◽  
Andrew Hebden ◽  
Dhongik Yoon ◽  
Erik Wilson ◽  
...  
Keyword(s):  
Fuel Element ◽  
Conceptual Design ◽  
Research Reactor ◽  
Reactor Design ◽  
Design Parameters ◽  
University Of Missouri ◽  
Flow Test

Application of best estimate thermal hydraulic code for safety analysis of high flux research reactor

2017 ◽  
Vol 6 (2) ◽  
pp. 109-117
Author(s):  
Samiran Sengupta ◽  
Vijay K. Veluri ◽  
R. Patel ◽  
S. Mammen ◽  
S. Bhattacharya
Keyword(s):  
Research Reactor ◽  
Safety Analysis ◽  
High Flux ◽  
Best Estimate

scholarly journals Measurement of the 13C(n,$\gamma$) thermal cross section via neutron irradiation and AMS

2019 ◽  
Vol 55 (11) ◽  
Author(s):  
T. Wright ◽  
S. Bennett ◽  
S. Heinitz ◽  
U. Köster ◽  
R. Mills ◽  
...  
Keyword(s):  
Activation Analysis ◽  
Cross Section ◽  
Research Reactor ◽  
Gamma Ray ◽  
Beam Line ◽  
Prompt Gamma ◽  
High Flux ◽  
Accelerator Mass Spectrometer ◽  
Thermal Cross Section ◽  
Good Agreement

Abstract.Ampoules of amorphous 99.5% enriched 13C were irradiated at the PF1b neutron beam line at the high-flux ILL research reactor in order to produce 14C atoms. The precise ratio of 14C/13C was subsequently measured at the VERA Accelerator Mass Spectrometer, allowing the 13C(n,$ \gamma$γ)14C thermal cross section to be accurately determined. This is the first measurement of this cross section at sub-eV energies via this technique and the result of $ 1.52 \pm 0.07$1.52±0.07 mb for the thermal cross section is in good agreement with other recent measurements which were performed via Prompt Gamma-ray Activation Analysis.

A conceptual high flux reactor design with scope for use in ADS applications

Pramana ◽  
2007 ◽  
Vol 68 (2) ◽  
pp. 151-159
Author(s):  
Usha Pal ◽  
V. Jagannathan
Keyword(s):  
Reactor Design ◽  
High Flux ◽  
High Flux Reactor ◽  
Flux Reactor

First wall ablations with high-flux pulsed proton beams and UV laser lights for IFE reactor design database

2006 ◽  
Vol 81 (8-14) ◽  
pp. 1653-1659 ◽  
Author(s):  
Koichi Kasuya ◽  
Yohsuke Kinoshita ◽  
Takayoshi Norimatsu ◽  
Sadao Nakai ◽  
Waldemar Mroz ◽  
...  
Keyword(s):  
Reactor Design ◽  
High Flux ◽  
Uv Laser ◽  
First Wall ◽  
Proton Beams ◽  
Design Database

scholarly journals Heat Transfer Calculation on Plate-Type Fuel Assembly of High Flux Research Reactor

2015 ◽  
Vol 2015 ◽  
pp. 1-13 ◽  
Author(s):  
Daxin Gong ◽  
Shanfang Huang ◽  
Guanbo Wang ◽  
Kan Wang
Keyword(s):  
Heat Transfer ◽  
Fuel Assembly ◽  
Research Reactor ◽  
Hot Spot ◽  
Saturation Temperature ◽  
High Flux ◽  
Turbulence Flow ◽  
Commercial Code ◽  
Fuel Assemblies ◽  
And Control

Heat transfer characteristics of fuel assemblies for a high flux research reactor with a neutron trap are numerically investigated in this study. Single-phase turbulence flow is calculated by a commercial code, FLUENT, where the computational objective covers standard and control fuel assemblies. The simulation is carried out with an inlet coolant velocity varying from 4.5 m/s to 7.5 m/s in hot assemblies. The results indicate that the cladding temperature is always lower than the saturation temperature in the calculated ranges. The temperature rise in the control fuel assembly is smaller than that of the standard fuel assembly. Additionally, the assembly with a hot spot is specially studied, and the safety of the research reactor is also approved.

Sign in / Sign up

Export Citation Format

Share Document