Research on single channel and subchannel in thermal-hydraulic analysis of TP-1 sodium cooled TWR

Hong Yang Wei; Wen Xi Tian; Teng Long Cong; Hao Huang; Guang Hui Su; Sui Zheng Qiu

doi:10.7538/yzk.2013.47.12.2261

Research on single channel and subchannel in thermal-hydraulic analysis of TP-1 sodium cooled TWR

Hong Yang Wei
, Wen Xi Tian
, Teng Long Cong
, Hao Huang
, Guang Hui Su
, Sui Zheng Qiu

能源与动力工程学院

Xi'an Jiaotong University
China General Nuclear Power Group

科研成果: 期刊稿件 › 文章 › 同行评审

1 引用（Scopus）

摘要

The average temperatures of coolant, cladding, and fuel rod of each subassembly of TP-1 sodium cooled traveling wave reactor (TWR) which was designed by TerraPower Co. were obtained by a single channel code TAST. The hottest subassembly was also identified by TAST. Temperature, velocity and pressure distributions in the hottest subassembly were calculated by the subchannel analysis code SACOS-Na. The results indicate that coupling the single channel analysis code TAST with the subchannel analysis code SACOS-Na can effectively improve the computational efficiency and enhance the safety of reactor design.

源语言	英语
页（从-至）	2261-2266
页数	6
期刊	Yuanzineng Kexue Jishu/Atomic Energy Science and Technology
卷	47
期	12
DOI	https://doi.org/10.7538/yzk.2013.47.12.2261
出版状态	已出版 - 12月 2013

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title = "Research on single channel and subchannel in thermal-hydraulic analysis of TP-1 sodium cooled TWR",

abstract = "The average temperatures of coolant, cladding, and fuel rod of each subassembly of TP-1 sodium cooled traveling wave reactor (TWR) which was designed by TerraPower Co. were obtained by a single channel code TAST. The hottest subassembly was also identified by TAST. Temperature, velocity and pressure distributions in the hottest subassembly were calculated by the subchannel analysis code SACOS-Na. The results indicate that coupling the single channel analysis code TAST with the subchannel analysis code SACOS-Na can effectively improve the computational efficiency and enhance the safety of reactor design.",

keywords = "Single channel, Sodium cooled traveling wave reactor, Subchannel",

author = "Wei, \{Hong Yang\} and Tian, \{Wen Xi\} and Cong, \{Teng Long\} and Hao Huang and Su, \{Guang Hui\} and Qiu, \{Sui Zheng\}",

year = "2013",

month = dec,

doi = "10.7538/yzk.2013.47.12.2261",

language = "英语",

volume = "47",

pages = "2261--2266",

journal = "Yuanzineng Kexue Jishu/Atomic Energy Science and Technology",

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TY - JOUR

T1 - Research on single channel and subchannel in thermal-hydraulic analysis of TP-1 sodium cooled TWR

AU - Wei, Hong Yang

AU - Tian, Wen Xi

AU - Cong, Teng Long

AU - Huang, Hao

AU - Su, Guang Hui

AU - Qiu, Sui Zheng

PY - 2013/12

Y1 - 2013/12

N2 - The average temperatures of coolant, cladding, and fuel rod of each subassembly of TP-1 sodium cooled traveling wave reactor (TWR) which was designed by TerraPower Co. were obtained by a single channel code TAST. The hottest subassembly was also identified by TAST. Temperature, velocity and pressure distributions in the hottest subassembly were calculated by the subchannel analysis code SACOS-Na. The results indicate that coupling the single channel analysis code TAST with the subchannel analysis code SACOS-Na can effectively improve the computational efficiency and enhance the safety of reactor design.

AB - The average temperatures of coolant, cladding, and fuel rod of each subassembly of TP-1 sodium cooled traveling wave reactor (TWR) which was designed by TerraPower Co. were obtained by a single channel code TAST. The hottest subassembly was also identified by TAST. Temperature, velocity and pressure distributions in the hottest subassembly were calculated by the subchannel analysis code SACOS-Na. The results indicate that coupling the single channel analysis code TAST with the subchannel analysis code SACOS-Na can effectively improve the computational efficiency and enhance the safety of reactor design.

KW - Single channel

KW - Sodium cooled traveling wave reactor

KW - Subchannel

UR - https://www.scopus.com/pages/publications/84897760574

U2 - 10.7538/yzk.2013.47.12.2261

DO - 10.7538/yzk.2013.47.12.2261

M3 - 文章

AN - SCOPUS:84897760574

SN - 1000-6931

VL - 47

SP - 2261

EP - 2266

JO - Yuanzineng Kexue Jishu/Atomic Energy Science and Technology

JF - Yuanzineng Kexue Jishu/Atomic Energy Science and Technology

IS - 12

ER -

Research on single channel and subchannel in thermal-hydraulic analysis of TP-1 sodium cooled TWR

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