Dispersion type absorbing materials for thermal reactor control rods

1964 ◽  
Vol 17 (2) ◽  
pp. 815-820
Author(s):  
V. I. Nosov ◽  
N. N. Ponomarev-Stepnoi ◽  
K. I. Portnoi ◽  
E. G. Savel'yev
Keyword(s):  
Thermal Reactor ◽  
Reactor Control ◽  
Absorbing Materials ◽  
Control Rods

Dispersion-type absorber materials for thermal reactor control rods

1965 ◽  
Vol 19 (9) ◽  
pp. 720-728
Author(s):  
V.I. Nosov ◽  
N.N. Ponomarev-stepnoi ◽  
K.I. Portnoi ◽  
E.G. Savel'ev
Keyword(s):  
Thermal Reactor ◽  
Reactor Control ◽  
Control Rods

Determination of Cadmium Burnup in Reactor Control Rods by Neutron Radiography

1964 ◽  
Vol 18 (2) ◽  
pp. 236-241 ◽  
Author(s):  
Harold Berger ◽  
James H. Talboy ◽  
Joseph P. Tylka
Keyword(s):  
Neutron Radiography ◽  
Reactor Control ◽  
Control Rods

A Reduced Basis Approach for Modeling the Movement of Nuclear Reactor Control Rods

2016 ◽  
Vol 2 (2) ◽  
Author(s):  
Alberto Sartori ◽  
Antonio Cammi ◽  
Lelio Luzzi ◽  
Gianluigi Rozza
Keyword(s):  
Neutron Flux ◽  
Nuclear Reactor ◽  
Voronoi Tessellation ◽  
Sampling Technique ◽  
Computational Time ◽  
High Fidelity ◽  
Reduced Basis ◽  
Reactor Control ◽  
Control Rods ◽  
Nuclear Reactor Control

This work presents a reduced order model (ROM) aimed at simulating nuclear reactor control rods movement and featuring fast-running prediction of reactivity and neutron flux distribution as well. In particular, the reduced basis (RB) method (built upon a high-fidelity finite element (FE) approximation) has been employed. The neutronics has been modeled according to a parametrized stationary version of the multigroup neutron diffusion equation, which can be formulated as a generalized eigenvalue problem. Within the RB framework, the centroidal Voronoi tessellation is employed as a sampling technique due to the possibility of a hierarchical parameter space exploration, without relying on a “classical” a posteriori error estimation, and saving an important amount of computational time in the offline phase. Here, the proposed ROM is capable of correctly predicting, with respect to the high-fidelity FE approximation, both the reactivity and neutron flux shape. In this way, a computational speedup of at least three orders of magnitude is achieved. If a higher precision is required, the number of employed basis functions (BFs) must be increased.

Operational Experience with and Postirradiation Examinations on Boiling Water Reactor Control Rods

1983 ◽  
Vol 60 (3) ◽  
pp. 362-366 ◽  
Author(s):  
Norbert Eickelpasch ◽  
Reinhard W. Seepolt ◽  
Johann Müllauer ◽  
Werner Spalthoff
Keyword(s):  
Boiling Water ◽  
Boiling Water Reactor ◽  
Operational Experience ◽  
Reactor Control ◽  
Water Reactor ◽  
Control Rods

scholarly journals On Line Measurement of Reactivity Worth of TRIGA Mark-II Research Reactor Control Rods

2011 ◽  
Vol 02 (09) ◽  
pp. 1024-1029 ◽  
Author(s):  
Nusrat Jahan ◽  
Mamunur M. Rashid ◽  
F. Ahmed ◽  
M. G. S. Islam ◽  
M. Aliuzzaman ◽  
...  
Keyword(s):  
Research Reactor ◽  
Reactor Control ◽  
Line Measurement ◽  
On Line ◽  
Triga Mark Ii ◽  
Control Rods
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