Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors

Hideaki Matsuura; Ryo Okamoto; Yuki Koga; Takuro Suganuma; Kazunari Katayama; Teppei Otsuka; Minoru Goto; Shigeaki Nakagawa; Etsuo Ishitsuka; Kenji Tobita

doi:10.1016/j.fusengdes.2019.02.009

Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors

Hideaki Matsuura, Ryo Okamoto, Yuki Koga, Takuro Suganuma, Kazunari Katayama, Teppei Otsuka, Minoru Goto, Shigeaki Nakagawa, Etsuo Ishitsuka, Kenji Tobita

ENG - Quantum Science and Energy Engineering

Research output: Contribution to journal › Article › peer-review

8 Citations (Scopus)

Abstract

Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prior engineering test with tritium handling and for the startup operation of a demonstration fusion reactor. For this purpose, the hydrogen absorption speed of Zr in a Li-loading rod for the reactor operation is experimentally measured, and an analysis model is presented to evaluate the tritium outflow from the Li rod in a high-temperature engineering test reactor (HTTR). On the basis of the presented model, the structure of the Li-loading rod for the demonstration test using the HTTR is proposed.

Original language	English
Pages (from-to)	1077-1081
Number of pages	5
Journal	Fusion Engineering and Design
Volume	146
DOIs	https://doi.org/10.1016/j.fusengdes.2019.02.009
Publication status	Published - 2019 Sept

Keywords

High-temperature gas-cooled reactor
HTTR
Lithium
Lithium-loading rod
Tritium
Zirconium

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10.1016/j.fusengdes.2019.02.009

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title = "Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors",

abstract = "Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prior engineering test with tritium handling and for the startup operation of a demonstration fusion reactor. For this purpose, the hydrogen absorption speed of Zr in a Li-loading rod for the reactor operation is experimentally measured, and an analysis model is presented to evaluate the tritium outflow from the Li rod in a high-temperature engineering test reactor (HTTR). On the basis of the presented model, the structure of the Li-loading rod for the demonstration test using the HTTR is proposed.",

keywords = "High-temperature gas-cooled reactor, HTTR, Lithium, Lithium-loading rod, Tritium, Zirconium",

author = "Hideaki Matsuura and Ryo Okamoto and Yuki Koga and Takuro Suganuma and Kazunari Katayama and Teppei Otsuka and Minoru Goto and Shigeaki Nakagawa and Etsuo Ishitsuka and Kenji Tobita",

note = "Funding Information: This work is supported by JSPS KAKENHI Grant-in-Aid for Scientific Research (B) JP18H1200 and cooperative program with BA (The Joint Implementation of the Broader Approach Activities in the Field of Fusion Energy Research) reactor design team in Japan. Publisher Copyright: {\textcopyright} 2019 Elsevier B.V.",

year = "2019",

month = sep,

doi = "10.1016/j.fusengdes.2019.02.009",

language = "English",

volume = "146",

pages = "1077--1081",

journal = "Fusion Engineering and Design",

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TY - JOUR

T1 - Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors

AU - Matsuura, Hideaki

AU - Okamoto, Ryo

AU - Koga, Yuki

AU - Suganuma, Takuro

AU - Katayama, Kazunari

AU - Otsuka, Teppei

AU - Goto, Minoru

AU - Nakagawa, Shigeaki

AU - Ishitsuka, Etsuo

AU - Tobita, Kenji

N1 - Funding Information: This work is supported by JSPS KAKENHI Grant-in-Aid for Scientific Research (B) JP18H1200 and cooperative program with BA (The Joint Implementation of the Broader Approach Activities in the Field of Fusion Energy Research) reactor design team in Japan. Publisher Copyright: © 2019 Elsevier B.V.

PY - 2019/9

Y1 - 2019/9

N2 - Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prior engineering test with tritium handling and for the startup operation of a demonstration fusion reactor. For this purpose, the hydrogen absorption speed of Zr in a Li-loading rod for the reactor operation is experimentally measured, and an analysis model is presented to evaluate the tritium outflow from the Li rod in a high-temperature engineering test reactor (HTTR). On the basis of the presented model, the structure of the Li-loading rod for the demonstration test using the HTTR is proposed.

AB - Production of tritium using a high-temperature gas-cooled reactor (HTGR) has been studied for a prior engineering test with tritium handling and for the startup operation of a demonstration fusion reactor. For this purpose, the hydrogen absorption speed of Zr in a Li-loading rod for the reactor operation is experimentally measured, and an analysis model is presented to evaluate the tritium outflow from the Li rod in a high-temperature engineering test reactor (HTTR). On the basis of the presented model, the structure of the Li-loading rod for the demonstration test using the HTTR is proposed.

KW - High-temperature gas-cooled reactor

KW - HTTR

KW - Lithium

KW - Lithium-loading rod

KW - Tritium

KW - Zirconium

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DO - 10.1016/j.fusengdes.2019.02.009

M3 - Article

AN - SCOPUS:85062679083

SN - 0920-3796

VL - 146

SP - 1077

EP - 1081

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

ER -

Li-rod structure in high-temperature gas-cooled reactor as a tritium production device for fusion reactors

Abstract

Keywords

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