Kinematic Analysis of Carrier Mechanism for In-service Inspection of Sodium-Cooled Fast Reactor Internals

2018 ◽  
pp. 247-256
Author(s):  
Sudheer Patri ◽  
Varun Kaushik ◽  
C. Meikandamurthy ◽  
B. K. Sreedhar ◽  
V. Prakash ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Kinematic Analysis ◽  
Carrier Mechanism ◽  
Service Inspection ◽  
Reactor Internals

An ultrasonic methodology for in-service inspection of shell weld of core support structure in a sodium cooled fast reactor

2015 ◽  
Vol 282 ◽  
pp. 83-92 ◽  
Author(s):  
Anish Kumar ◽  
K.V. Rajkumar ◽  
Govind K. Sharma ◽  
R. Dhayalan ◽  
T. Jayakumar
Keyword(s):  
Fast Reactor ◽  
Support Structure ◽  
Service Inspection

Design and Manufacture of the Storage Cask for the Old Reactor Internals

2006 ◽  
Author(s):  
Yasuhiro Tomiita
Keyword(s):  
Electric Power ◽  
Extraction Method ◽  
Reactor Vessel ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Key Points ◽  
Design And Manufacture ◽  
Service Inspection ◽  
Reactor Internals

Mitsubishi Heavy Industries, Ltd. (MHI) completed replacement work of upper reactor internals (UCI) and lower reactor internals (LCI) of the pressurized water reactor in Shikoku Electric Power Company’s Ikata Unit No.1 by “the all-in-one-piece extraction method” introduced in the document of [ICONE14-89233]. In the pressurized water reactor (PWR) plant, the UCI are usually removed from the reactor vessel (RV) independently and reinstalled into the RV again every refueling outage. The LCI are independently able to be removed from the RV and reinstalled again during in-service inspection, too. In the boiling water reactor (BWR) plant, there are several cases of replacing BWR shrouds by cutting small and containing in a container. But no replacement of all reactor internals (CI) for the PWR, in one piece without splitting or cutting, has been reported. The purpose of this paper is to introduce the key points about the design and manufacture of the storage cask for old reactor internals in the replacement work by “the all-in-one-piece extraction method”.

Study on In-Service Inspection Program and Inspection Technologies for Commercialized Sodium-Cooled Fast Reactor

2006 ◽  
Author(s):  
Masato Ando ◽  
Shigenobu Kubo ◽  
Yoshio Kamishima ◽  
Toru Iitsuka
Keyword(s):  
Steam Generator ◽  
Fast Reactor ◽  
Nuclear Power ◽  
Boundary Function ◽  
Sodium Coolant ◽  
Cycle Systems ◽  
And Performance ◽  
Double Wall ◽  
Wall System ◽  
Service Inspection

The objective of in-service inspection of a nuclear power plant is to confirm integrity of function of components necessary to safety, and satisfy the needs to protect plant investment and to achieve high plant ability. The sodium-cooled fast reactor, which is designed in the feasibility study on commercialized fast reactor cycle systems in Japan, has two characteristics related to in-service inspection. The first is that all sodium coolant boundary structures have double-wall system. Continuous monitoring of the sodium coolant boundary structures are adopted for inspection. The second characteristic is the steam generator with double-wall-tubes. Volumetric testing is adopted to make sure that one of the tubes can maintain the boundary function in case of the other tube failure. A rational in-service inspection concept was developed taking these features into account. The inspection technologies were developed to implement in-service inspection plan. The under-sodium viewing system consisted of multi ultrasonic scanning transducers, which was used for imaging under-sodium structures. The under-sodium viewing system was mounted on the under-sodium vehicle and delivered to core internals. The prototype of under-sodium viewing system and vehicle were fabricated and performance tests were carried out under water. The laboratory experiments of volumetric testing for double-wall-tubes of steam generator, such as ultrasonic testing and remote-field eddy current testing, were performed and technical feasibility was assessed.

scholarly journals Determination of in-service inspection requirements for fast reactor components using System Based Code concept

2016 ◽  
Vol 305 ◽  
pp. 270-276 ◽  
Author(s):  
Shigeru Takaya ◽  
Yoshio Kamishima ◽  
Hideo Machida ◽  
Daigo Watanabe ◽  
Tai Asayama
Keyword(s):  
Fast Reactor ◽  
Service Inspection

Kinematic Approximations in TED and RHEED Analysis of Reconstructed Surfaces

1990 ◽  
Vol 48 (2) ◽  
pp. 396-397
Author(s):  
L. -M. Peng ◽  
M. J. Whelan
Keyword(s):  
Electron Diffraction ◽  
Kinematic Analysis ◽  
Incident Beam ◽  
High Energy ◽  
Energy Electron ◽  
Great Success ◽  
High Energy Electron ◽  
Kinematic Approximation ◽  
Reconstructed Surfaces

In recent years there has been a trend in the structure determination of reconstructed surfaces to use high energy electron diffraction techniques, and to employ a kinematic approximation in analyzing the intensities of surface superlattice reflections. Experimentally this is motivated by the great success of the determination of the dimer adatom stacking fault (DAS) structure of the Si(111) 7 × 7 reconstructed surface.While in the case of transmission electron diffraction (TED) the validity of the kinematic approximation has been examined by using multislice calculations for Si and certain incident beam directions, far less has been done in the reflection high energy electron diffraction (RHEED) case. In this paper we aim to provide a thorough Bloch wave analysis of the various diffraction processes involved, and to set criteria on the validity for the kinematic analysis of the intensities of the surface superlattice reflections.The validity of the kinematic analysis, being common to both the TED and RHEED case, relies primarily on two underlying observations, namely (l)the surface superlattice scattering in the selvedge is kinematically dominating, and (2)the superlattice diffracted beams are uncoupled from the fundamental diffracted beams within the bulk.

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