E216 Development of advanced high reliable helical type double wall tube steam generator

2009 ◽  
Vol 2009.14 (0) ◽  
pp. 461-462
Author(s):  
Noboru JIMBO ◽  
Kunio SHIMANO ◽  
Shigeki MARUYAMA ◽  
Noriyasu KOBAYASHI ◽  
Takehisa HINO
Keyword(s):  
Steam Generator ◽  
Double Wall

ICONE19-43935 Development of a Helical-Coil Double Wall Tube Steam Generator for 4S Reactor

2011 ◽  
Vol 2011.19 (0) ◽  
pp. _ICONE1943-_ICONE1943
Author(s):  
Yuko Kitajima ◽  
Takehisa Hino ◽  
Katsuhiko Sato ◽  
Shigeki Maruyama ◽  
Noboru Jimbo
Keyword(s):  
Steam Generator ◽  
Helical Coil ◽  
Double Wall

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.

A High Reliability Straight Tube LMFBR Steam Generator Design

1980 ◽  
Vol 102 (3) ◽  
pp. 568-572 ◽  
Author(s):  
A. H. Spring ◽  
D. D. DeFur
Keyword(s):  
Thermal Expansion ◽  
Steam Generator ◽  
High Reliability ◽  
Straight Tube ◽  
Steam Generators ◽  
Geometric Size ◽  
Differential Thermal Expansion ◽  
Generator Design ◽  
Double Wall ◽  
Reliability And Availability

Straight-tube counterflow steam generators for LMFBR applications have been proposed, tested, fabricated and operated with varying degrees of success. A new embodiment of the straight-tube concept is described which incorporates a number of unique features which contribute to high reliability and availability. These features include a replaceable bellows for accommodation of differential thermal expansion between shell and tubes and a redundant, crevice-free tube-to-tubesheet joint design. The design can also easily incorporate single-wall or double-wall tubes. Single and double-wall tube versions are described whose thermal and geometric size are based on anticipated manufacturing limitations. The results of scoping tests of the tube-to-tubesheet welds are described which provide positive indications of the soundness of the weld design.

NUMERICAL SIMULATION OF DRYOUT CHARACTERISTICS OF THE HELICAL ONCE-THROUGH STEAM GENERATOR

2018 ◽  
Author(s):  
Xiang Yu ◽  
Baozhi Sun ◽  
Jianxin Shi ◽  
Wanze Wu ◽  
Zhirui Zhao
Keyword(s):  
Numerical Simulation ◽  
Steam Generator
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