scholarly journals Effect of Kinetic Parameters on Simultaneous Ramp Reactivity Insertion Plus Beam Tube Flooding Accident in a Typical Low Enriched U 3 Si 2 -Al Fuel-Based Material Testing Reactor-Type Research Reactor

2017 ◽  
Vol 49 (4) ◽  
pp. 700-709 ◽  
Author(s):  
Rubina Nasir ◽  
Sikander M. Mirza ◽  
Nasir M. Mirza
Keyword(s):  
Kinetic Parameters ◽  
Research Reactor ◽  
Material Testing ◽  
Beam Tube ◽  
Reactor Type ◽  
Reactivity Insertion

scholarly journals Determination of backscattered neutrons/gammas from open beam port of a research reactor

2020 ◽  
Vol 225 ◽  
pp. 04032
Author(s):  
Anže Jazbec ◽  
Bor Kos ◽  
Vladimir Radulović ◽  
Klemen Ambrožič ◽  
Luka Snoj
Keyword(s):  
Research Reactor ◽  
Gamma Dose ◽  
Computation Model ◽  
Beam Tube ◽  
Horizontal Beam ◽  
Beam Port ◽  
Jozef Stefan Institute ◽  
Stefan Institute ◽  
Triga Mark Ii

Neutron and gamma dose rate calculations were carried out around horizontal beam tube no. 5 at the Jožef Stefan Institute (JSI) TRIGA Mark II research reactor. Results were compared to the experimental measurements in order to verify the computation model. In addition, another set of calculations and measurements was carried out, where an additional shield made out of concrete and paraffin was installed. With that configuration, we were able to study neutron and gamma scattering.

scholarly journals Kinetic parameters study based on burn-up for improving the performance of research reactor equilibrium core

2014 ◽  
Vol 29 (4) ◽  
pp. 253-258 ◽  
Author(s):  
Atta Muhammad ◽  
Masood Iqbal ◽  
Tayyab Mahmood
Keyword(s):  
Kinetic Parameters ◽  
Generation Time ◽  
Research Reactor ◽  
Prompt Neutron ◽  
Neutron Generation ◽  
Delayed Neutron ◽  
Fuel Burn ◽  
Hard Spectrum ◽  
Computer Codes ◽  
Enriched Uranium

In this study kinetic parameters, effective delayed neutron fraction and prompt neutron generation time have been investigated at different burn-up stages for research reactor's equilibrium core utilizing low enriched uranium high density fuel (U3Si2-Al fuel with 4.8 g/cm3 of uranium). Results have been compared with reference operating core of Pakistan research Reactor-1. It was observed that by increasing fuel burn-up, effective delayed neutron fraction is decreased while prompt neutron generation time is increased. However, over all ratio beff/L is decreased with increasing burn-up. Prompt neutron generation time L in the understudy core is lower than reference operating core of reactor at all burn-up steps due to hard spectrum. It is observed that beff is larger in the understudy core than reference operating core of due to smaller size. Calculations were performed with the help of computer codes WIMSD/4 and CITATION.

Validation of SIMMER-III Neutronics Module for the Simulation of Reactivity Injection Accident in Material Testing Reactors

2010 ◽  
Author(s):  
Yacine Chegrani ◽  
Corinne d’Aletto ◽  
Jacques Di Salvo ◽  
Evgeny Ivanov
Keyword(s):  
Kinetic Parameters ◽  
Reference Model ◽  
Reactor Core ◽  
Material Testing ◽  
Thermal Hydraulics ◽  
Nuclear Plants ◽  
Modeling Material ◽  
Transport And Diffusion ◽  
And Diffusion ◽  
Good Agreement

The “Institut de Radioprotection et de Suˆrete´ Nucle´aire”, as the technical support of the French Safety Authority, carries out studies and research to analyze and assess the safety of all nuclear plants. In this frame IRSN studies the feasibility of modeling Material Testing Reactor core with SIMMER-III code, for simulation of reactivity initiated accidental transients. The SIMMER-III multi-physics code system was initially developed for mechanistic safety analyses of liquid metal cooled fast reactors while employing coupled spatial neutron kinetics and thermal hydraulics models. Neutronics and thermal-hydraulics SIMMER-III models have been extended to safety analyses for water cooled and moderated reactors. The use of a code like SIMMER-III requires approximations; it computes a simplified R-Z geometry and chemistry description of the core that must be validated. The methods applied consist here in developing models of the same reactor on several scales of detail. The first step is the validation of the cross section condensation for deterministic APOLLO2 calculation against Monte Carlo TRIPOLI4 2D model. Temperature effects, kinetic parameters and void coefficients on the whole core are then calculated on a 2D APOLLO2 model, using the Method of Characteristics. These parameters are also computed with a 3D combined transport and diffusion calculations by means of APOLLO2/CRONOS2 calculations, validated against a TRIPOLI4 3D precise reference model. The final step is the validation of the simmer-like R-Z geometry in APOLLO2 Sn and Pij. Finally, an R-Z geometry has been computed in SIMMER-III, for the calculation of the kinetic parameters and temperature coefficients. This validation method has been applied to Jules Horowitz Reactor, a French Material Testing Reactor currently in commissioning by the CEA. This leads to conclude that discrepancies due to simplifications are acceptable. Moreover SIMMER-III shows quite a good agreement with CEA ring calculation on the kinetic parameters. Concerning neutronics feedbacks coefficients, further analyses remain necessary.

Sign in / Sign up

Export Citation Format

Share Document