Neutronic analysis of absorbing materials for the control rod system in reactor ALLEGRO

Kerntechnik ◽  
2016 ◽  
Vol 81 (4) ◽  
pp. 445-451
Author(s):  
F. Čajko ◽  
M. Sečanský ◽  
T. Chrebet ◽  
R. Zajac ◽  
P. Dařílek
Keyword(s):  
Control Rod ◽  
Rod System ◽  
Absorbing Materials

Comparative Analysis of the Control Rod Drive System

2012 ◽  
Vol 614-615 ◽  
pp. 1558-1561
Author(s):  
Wen Wei Han ◽  
Wei Shi Han ◽  
Qing Guo
Keyword(s):  
Comparative Analysis ◽  
Drive System ◽  
Hydraulic Control ◽  
Control Rod ◽  
Rod System ◽  
Drive Systems ◽  
Research Situation

This article has systematically summarized the recent research situation of control rod system in China and comparatively analyzed the features of a variety of control rod drive systems on a basis of brief introduction of common types of control rod drive system. It has been proposed to that the hydraulic control rod drive system have a great potential in a wide application concerning on ships, warships power reactors and protable desalination system.

ICONE15-10466 DESIGN OF THE CONTROL ROD SYSTEM FOR THE 2400 MW_ GENERATION IV GAS-COOLED FAST REACTOR

2007 ◽  
Vol 2007.15 (0) ◽  
pp. _ICONE1510-_ICONE1510
Author(s):  
G. Girardin ◽  
P. Coddington ◽  
F. Morin ◽  
G. Rimpault ◽  
R. Chawla
Keyword(s):  
Fast Reactor ◽  
Control Rod ◽  
Rod System

Design and tests for the HTR-10 control rod system

2002 ◽  
Vol 218 (1-3) ◽  
pp. 147-154 ◽  
Author(s):  
Wu Yuanqiang ◽  
Diao Xingzhong ◽  
Zhou Huizhong ◽  
Huang Zhiyong
Keyword(s):  
Control Rod ◽  
Rod System

Research of the Rod Drop Time Based on the Control Rod System of TMSR-SF1

2017 ◽  
Author(s):  
Zuokang Lin ◽  
Lin Zhu ◽  
Chunfeng Zhao ◽  
Yun Cao ◽  
Xiao Wang
Keyword(s):  
Molten Salt ◽  
Similarity Criterion ◽  
Maximum Error ◽  
Driving Mechanism ◽  
Control Rod ◽  
Water Condition ◽  
Rod System ◽  
Drop Time ◽  
Control Rods ◽  
Reactor Accidents

The reactor scram function realized by the rapidly dropping of control rods ensures safety when the reactor accidents (loss of electricity and earthquake, etc.) happen. In the thorium base molten salt reactor (TMSR - SF1), the rod drop time is obviously affected by the resistance which produced in the molten salt as its high density and viscosity. In this paper, the drop time of the control rod is obtained by the theoretical and experimental methods for comparison. Firstly, the drop time is analyzed both in air and water condition with calculation and experiment. And the method used for the resistance calculation of the rod during dropping is verified. Secondly, the similarity criterion is adopted to calculate the drop time in molten salt condition. The study shows that: 1) In air and water condition, the calculation is coincidence with the experimental results within the maximum error less than 2 %. 2) The drop time of the rod in molten salt is 2.8 s with a dropping height 2.4m in reactor, which satisfy the safety requirement of the control system. 3) It is necessary to use another buffer beside the disc spring to protect the driving mechanism of the rod during the rod dropping.

scholarly journals Structure Optimization Design of the Electronically Controlled Fuel Control Rod System in a Diesel Engine

2015 ◽  
Vol 2015 ◽  
pp. 1-10
Author(s):  
Hui Jin ◽  
Haosen Wang
Keyword(s):  
Cooperative Control ◽  
Optimization Design ◽  
Engine Speed ◽  
Ride Comfort ◽  
Key Factors ◽  
Control Rod ◽  
Rod System ◽  
Design Cycle ◽  
Vehicle Systems ◽  
Automated Manual Transmission

Poor ride comfort and shorter clutch life span are the key factors restricting the commercialization of automated manual transmission (AMT). For nonelectrically controlled engines or AMT where cooperative control between the engine and the transmission is not realizable, applying electronically controlled fuel control rod systems (ECFCRS) is an effective way to solve these problems. By applying design software such as CATIA, Matlab and Simulink, and MSC Adams, a suite of optimization design methods for ECFCRS drive mechanisms are developed here. Based on these new methods, design requirements can be analyzed comprehensively and the design scheme can be modified easily, thus greatly shortening the design cycle. The bench tests and real vehicle tests indicate that the system developed achieves preferable engine speed following-up performance and engine speed regulating performance. The method developed has significance as a reference for developing other vehicle systems.

Study on the Rod Drop Performance of High-Temperature Gas-Cooled Reactor

2014 ◽  
Author(s):  
He Yan ◽  
Xingzhong Diao
Keyword(s):  
High Temperature ◽  
Pressure Vessel ◽  
Reactor Core ◽  
Insertion Time ◽  
Operational Mode ◽  
Control Rod ◽  
Rod System ◽  
Key Factor ◽  
Control Rods ◽  
High Temperature Gas

In this paper, the theoretical study and experimental investigation on the rod drop performance of high-temperature gas-cooled reactor (HTGR) pebble-bed module have been presented. The control rod drive mechanisms (CRDMs), serving as the first shutdown system of the reactor, are positioned above the reactor pressure vessel. When the reactor is operated at the power regulation mode, the control rods are pulled up-and-down in their channels around the reactor core. The CRDM provides a fail-safe operational mode for the control rod system. If the reactor emergency shutdown is required the control rods could drop into their channels by gravity. Thus the key factor, emergency insertion time of the whole control rod stroke, which represents the inherent safety of the CRDM, is crucially important and should be measured precisely. In the final objective of ensuring reliability of the CRDM, a full size drive line had been built and tested to obtain the overall performance function of the CRDM. Every component of the CRDM test line was simulated at the scale 1:1, including a 15 meters high test bench that was used as the substitution of the pressure vessel. At current stage, the rod drop performance had been experimental investigated at ambient temperature and pressure. The emergency insertion time of an 8 meters stroke was measured to be less than 50 seconds. A mathematical model of CRDM also had been developed. The rod motion characteristic equations show that the rod dropping speed approaches to a constant during the emergency insertion. The theoretical results are in agreement with the test results.

scholarly journals Feasibility study of the university of Utah TRIGA reactor power upgrade - Part I: Neutronics-based study in respect to control rod system requirements and design

2013 ◽  
Vol 28 (2) ◽  
pp. 109-117 ◽  
Author(s):  
Avdo Cutic ◽  
Dongok Choe ◽  
Tatjana Jevremovic
Keyword(s):  
Numerical Models ◽  
Power Level ◽  
Feasibility Studies ◽  
Reactor Power ◽  
Control Rod ◽  
University Of Utah ◽  
Wide Range ◽  
Rod System ◽  
The University ◽  
Fuel Elements

We present a summary of extensive studies in determining the highest achievable power level of the current University of Utah TRIGA core configuration in respect to control rod requirements. Although the currently licensed University of Utah TRIGA power of 100 kW provides an excellent setting for a wide range of experiments, we investigate the possibility of increasing the power with the existing fuel elements and core structure. Thus, we have developed numerical models in combination with experimental procedures so as to assess the potential maximum University of Utah TRIGA power with the currently available control rod system and have created feasibility studies for assessing new core configurations that could provide higher core power levels. For the maximum determined power of a new University of Utah TRIGA core arrangement, a new control rod system was proposed.

PAPER 2.10 STUDIES ON THE SNR CONTROL ROD SYSTEM

1969 ◽  
pp. 295-298
Author(s):  
K. H. Joest ◽  
H. Hübel ◽  
St. Beliczey ◽  
J. Heinecke ◽  
W. Löhr ◽  
...  
Keyword(s):  
Control Rod ◽  
Rod System

Measurement system for calibrating the neutron apparatus of the control-rod system of transport nuclear power-generating systems

Atomic Energy ◽  
2000 ◽  
Vol 88 (5) ◽  
pp. 402-407
Author(s):  
V. D. Sevast'ynov ◽  
V. P. Yaryna ◽  
A. E. Volkov ◽  
V. D. Pavlov
Keyword(s):  
Measurement System ◽  
Nuclear Power ◽  
Control Rod ◽  
Rod System
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