Regulation of nuclear reactors by duplexed control rods: linearized analysis

1991 ◽  
Vol 38 (5) ◽  
pp. 1044-1051
Author(s):  
N.H.S. Haidar ◽  
H.B. Diab
Keyword(s):  
Nuclear Reactors ◽  
Control Rods

Volatilization of B4C control rods in Fukushima Daiichi nuclear reactors during meltdown: B–Li isotopic signatures in cesium-rich microparticles

2022 ◽  
pp. 128214
Author(s):  
Kazuki Fueda ◽  
Ryu Takami ◽  
Kenta Minomo ◽  
Kazuya Morooka ◽  
Kenji Horie ◽  
...  
Keyword(s):  
Nuclear Reactors ◽  
Isotopic Signatures ◽  
Fukushima Daiichi ◽  
Control Rods

Prediction of the lifetime of the elements of the safety and control rods of nuclear reactors

1987 ◽  
Vol 62 (1) ◽  
pp. 20-28
Author(s):  
V. V. Voskoboinikov ◽  
I. Ya. Emel'yanov ◽  
A. F. Lineva ◽  
S. N. Pushkin ◽  
�. L. Semchenko ◽  
...  
Keyword(s):  
Nuclear Reactors ◽  
And Control ◽  
Control Rods

Design, construction and simulation of a multipurpose system for precision movement of control rods in nuclear reactors

2010 ◽  
Vol 37 (12) ◽  
pp. 1659-1665 ◽  
Author(s):  
S.A. Mousavi Shirazi ◽  
C. Aghanajafi ◽  
S. Sadoughi ◽  
N. Sharifloo
Keyword(s):  
Nuclear Reactors ◽  
Control Rods ◽  
Design Construction

scholarly journals Irradiation Assisted Mechanical Cracking on Cladding Tubes of Control Rods in Nuclear Reactors.

1999 ◽  
Vol 42 (3) ◽  
pp. 438-446 ◽  
Author(s):  
Takanori MATSUOKA ◽  
Youichirou YAMAGUCHI ◽  
Toshio YONEZAWA ◽  
Kazuhiro NAKAMURA ◽  
Riyou FUKUDA ◽  
...  
Keyword(s):  
Nuclear Reactors ◽  
Control Rods

Release of 108Ag from Irradiated PWR Control Rod Absorbers under Deep Repository Conditions

2015 ◽  
Vol 1744 ◽  
pp. 217-222
Author(s):  
O. Roth ◽  
M. Granfors ◽  
A. Puranen ◽  
K. Spahiu
Keyword(s):  
Nuclear Fuel ◽  
Source Term ◽  
Spent Nuclear Fuel ◽  
Nuclear Reactors ◽  
Reactor Irradiation ◽  
Spent Fuel ◽  
Control Rod ◽  
Potential Source ◽  
Absorber Material ◽  
Control Rods

ABSTRACTIn a future Swedish deep repository for spent nuclear fuel, irradiated control rods from PWR nuclear reactors are planned to be stored together with the spent fuel. The control rod absorber consists of an 80% Ag, 5% Cd, 15% In alloy with a steel cladding. Upon in-reactor irradiation 108Ag is produced by neutron capture. Release of 108Ag has been identified as a potential source term for release of radioactive substances from the deep repository.Under reducing deep repository conditions, the Ag corrosion rate is however expected to be low which would imply that the release rate of 108Ag should be low under these conditions. The aim of this study is to investigate the dissolution of PWR control rod absorber material under conditions relevant to a future deep repository for spent nuclear fuel. The experiments include tests using irradiated control rod absorber material from Ringhals 2, Sweden. Furthermore, un-irradiated control rod absorber alloy has been tested for comparison. The experiments indicate that the release of Ag from the alloy when exposed to water is strongly dependent on the redox conditions. Under aerated conditions Ag is released at a significant rate whereas no release could be measured after 133 days during leaching under H2.

Verification of the stationary module of the ShIPR software system for modelling experiments of the ASTRA HTGR type critical facility

Kerntechnik ◽  
2020 ◽  
Vol 85 (1) ◽  
pp. 4-8
Author(s):  
M. N. Zizin ◽  
V. F. Boyarinov ◽  
V. A. Nevinitsa ◽  
P. A. Fomichenko ◽  
Yu. N. Volkov ◽  
...  
Keyword(s):  
Cross Sections ◽  
Nuclear Reactors ◽  
Reaction Rates ◽  
Automatic Generation ◽  
Hydraulic Calculation ◽  
Monte Carlo Code ◽  
Fission Reaction ◽  
Development Environment ◽  
Transient Conditions ◽  
Control Rods

Abstract Coupled neutronic and thermal hydraulic calculation codes are verified for calculating the design of modern and prospective types of nuclear reactors. This verification is done by comparing experimental and calculated results for stationary and transient conditions. This paper presents ShIPR (Shell of Intelligent Package for Reactor) Integrated Development Environment with automatic generation of head programs based on the chain of computational modules. The aim of this study is to find the reason of a discrepancy in the modelling of sub-critical states that was found in previous work. The comparison of ShIPR stationary module with Monte-Carlo code (MCU) and experimental results on ASTRA HTGR critical facility was presented in the paper. To compare the detector readings and MCU calculation with the ShIPR module, the interpolation cross-section procedure was performed. This procedure allows simulating 235U fission reaction rates (detector readings) in the complicate, annular core, using the micro-cross sections prepared by the cell-lattice code. We found that the calculation accuracy of stationary ShIPR module is on an acceptable level but the macro constants for control rods need to be prepared independently, given with surroundings.

The Properties Research of Hafnium Plate for Control Rod

2011 ◽  
Vol 337 ◽  
pp. 494-497
Author(s):  
Hong Wen Huang ◽  
Xiang Miao Mi ◽  
Shan Zhou
Keyword(s):  
Mechanical Properties ◽  
Corrosion Resistance ◽  
Elemental Composition ◽  
Nuclear Reactors ◽  
Physical Characteristics ◽  
Control Rod ◽  
Manufacturing Method ◽  
Comprehensive Performance ◽  
Control Rods

Metallic hafnium has good comprehensive performance that makes it the preferred material for control rods of nuclear reactors. The elemental composition, mechanical properties, the corrosion resistance and the physical characteristics of hafnium plate are researched during the development of control rod for reactors. It proved the manufacturing method of hafnium plate is appropriate, characteristic of materials meet the requirement of a control rod.

Developments of the Hydraulic Driving System of the Control Rods for Nuclear Reactors

1999 ◽  
Author(s):  
Yuanqiang Wu
Keyword(s):  
Nuclear Reactor ◽  
Nuclear Reactors ◽  
Reactor Core ◽  
Hydraulic Pressure ◽  
Energy Agency ◽  
Control Rod ◽  
Driving System ◽  
History Of ◽  
The Cost ◽  
Control Rods

Abstract The developments of a new hydraulic driving system of the control rods for nuclear reactors are introduced in this paper. Compared with other driving systems of the control rods, this new hydraulic driving system can be set within the reactor pressure vessel. Under any serious condition, the control rods will not be ejected from the reactor core. Its structure is very simple and the mechanic chain is very short, and thus it is very reliable. It can reduce the height of the nuclear reactor by one-third, and thus dramatically reduce the cost of the reactor. It uses the dynamic hydraulic pressure to control the motion of the control rods. Under extreme conditions, such as the failure of control power supply, the control rods will drop into the reactor core because of their self-weight to shut down the nuclear reaction. Because of these features, International Atomic Energy Agency (IAEA) is very interested in this safe and economical new control rod driving system. A brief history of the developments of the hydraulic driving system is given. Three configurations, the orifice hydraulic step cylinder, the groove-orifice hydraulic step cylinder, and the piston-groove hydraulic step cylinder, are introduced and their working principles are explained. The reliability and safety of the new system are validated by two experimental works: hydraulic step cylinder (HSC) under seismic and rocking conditions. Results from these experiments are presented.

scholarly journals Next generation control rods for fast neutron nuclear reactors

2020 ◽  
Vol 1475 ◽  
pp. 012019 ◽  
Author(s):  
V D Risovany ◽  
A V Zakharov
Keyword(s):  
Fast Neutron ◽  
Nuclear Reactors ◽  
Next Generation ◽  
Control Rods ◽  
Generation Control
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