• 제목/요약/키워드: Nuclear engineering

검색결과 9,560건 처리시간 0.037초

Development of the vapor film thickness correlation in porous corrosion deposits on the cladding in PWR

  • Yuan Shen;Zhengang Duan;Chuan Lu ;Li Ji ;Caishan Jiao ;Hongguo Hou ;Nan Chao;Meng Zhang;Yu Zhou;Yang Gao
    • Nuclear Engineering and Technology
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    • 제54권12호
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    • pp.4798-4808
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    • 2022

  • The porous corrosion deposits (known as CRUD) adhered to the cladding have an important effect on the heat transfer from fuel rods to coolant in PWRs. The vapor film is the main constituent in the two-phase film boiling model. This paper presents a vapor film thickness correlation, associated with CRUD porosity, CRUD chimney density, CRUD particle size, CRUD thickness and heat flux. The dependences of the vapor film thickness on the various influential factors can be intuitively reflected from this vapor film thickness correlation. The temperature, pressure, and boric acid concentration distributions in CRUD can be well predicted using the two-phase film boiling model coupled with the vapor film thickness correlation. It suggests that the vapor thickness correlation can estimate the vapor film thickness more conveniently than the previously reported vapor thickness calculation methods.

  • https://doi.org/10.1016/j.net.2022.08.013 인용 PDF KSCI

PWSCC and System Engineering Development of Internal Inspection and Maintenance Methodology for RCS

  • Abdallah, Khaled Atya Ahmed;Mesquita, Patricia Alves Franca de;Yusoff, Norashila;Nam, GungIhn;Jung, JaeCheon;Lee, YoungKwan
    • 시스템엔지니어링학술지
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    • 제12권1호
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    • pp.89-103
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    • 2016

  • Due to safety of the plant, it became very clear the importance of study occurrence reactor coolant system (RCS) issues specially the primary water stress corrosion cracking (PWSCC). The Systems Engineering (SE) approach is characterized by the application of a structured engineering methodology for the design of a complex system or component. Robotic devices have been used for internal inspection, maintenance and performing remote welding and inspection in high-radiation areas. In this paper, PWSCC overview and inlay and over lay welding methodology introduced, concept of robotic device that can be inserted into the piping via Steam Generator (SG) main way to access to primary piping of pressurized water reactor (PWR) is developed based on SE methodology. A 3D model of the inspection system was developed along with the APR1400 (Advanced Power Reactor)reactor coolant systems (RCS) and internals with virtual 3D simulation of the operation for visualization to prove the validity of the concept.

  • https://doi.org/10.14248/JKOSSE.2016.12.1.089 인용 PDF KSCI