Jun-ichi TOYOOKA

New technology development expected for advanced reactors toward massive expansion of renewable energy capacity (1)

Hidemasa Yamano, Jun-ichi TOYOOKA

2050年カーボンニュートラルの実現に向けて，わが国は原子力エネルギーと共に再生可能エネルギー(再エネ)の電源比率を引き上げる一方，火力発電の比率をできる限り引き下げる方針である。しかしながら，当面の間，化石燃料による火力発電は太陽光発電や風力発電のもつ再エネの変動性を補う調整力としての役割を果たす必要がある。次世代革新炉(新型炉)は，再エネの変動性を補う調整力という新たな価値を有しており，原子力の新たな活用方法を提起することができる。本稿では，再エネ導入拡大を見据えた新型炉に期待される新たな技術開発として，国際原子力機関(IAEA)と第4世代原子力国際フォーラム(GIF)の取組を中心に，再エネ協調技術開発(統合エネルギーシステム，蓄熱，熱利用，水素製造)の国内外動向を紹介する。

Development trends of advanced reactor with a focus on fast reactor and high temperature gas-cooled reactor

Jun-ichi TOYOOKA, Shigenobu Kubo, Masahiro Nishimura, Hideki Kamide

脱炭素目標の達成やエネルギー安全保障の確保を背景に世界の原子力開発が加速している。ここでは，革新的な軽水炉，第4世代炉としての高速炉，高温ガス炉など革新炉の国際的な開発動向について小型モジュール炉(SMR)，規制基準，新しい製造技術に着目して解説する。

Forefront of development of next-generation innovative nuclear reactors (fast reactor and high-temperature gas-cooled reactor)

Hidemasa Yamano, Jun-ichi TOYOOKA, Hiroyuki Satō, Nariaki Sakaba

近年，国内外において革新炉導入に向けた活発な動きが見られる。米国では，2020年に「新型炉実証プログラム(ARDP)」を開始し，高速炉，高温ガス炉，マイクロ炉，溶融塩炉，軽水型小型モジュール炉(SMR)のプロジェクトが進められている。カナダ，仏国，英国，ポーランド，ロシア，中国，インドでも同様に新型炉開発が盛んになってきている。新型炉開発は原子力研究・開発の将来を開拓する技術分野であり，現在，原子力業界に求められているイノベーションの実現を目標としていることから，若い世代を原子力研究・開発へと惹きつけるもっとも魅力的な分野のひとつである。本稿では，主要な開発国を対象に最新の国外の次世代革新炉(高速炉と高温ガス炉を中心に)開発動向を紹介するとともに，国内においてはGX(グリーン・トランスフォーメーション)実現に向けた基本方針に則った次世代革新炉開発の動向を紹介する。

R&D and Experimental Programs to support the ASTRID Core Assessment in Severe Accidents Conditions

Frederic Serre, F. Payot, C. Suteau, L. Trotignon et autres

The ASTRID reactor (Advanced Sodium Technological Reactor for Industrial Demonstration) is a technological prototype designed by the CEA with its industrial partners, with very high levels of requirements. Innovative options have been integrated to enhance the safety, to reduce the capital cost …

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Experimental discussion on fragmentation mechanism of molten oxide discharged into a sodium pool

Ken-ichi Matsuba, Kenji Kamiyama, Jun-ichi TOYOOKA, Yoshiharu Tobita et autres

In a probable scenario for core disruptive accidents of Sodium-cooled Fast Reactors (SFRs), it is foreseen that molten core material would be discharged into lower sodium plenums through control rod guide tubes. Such material relocation might lead to a considerable thermal load …

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ICONE23-1603 EXPERIMENTAL DISCUSSION ON FRAGMENTATION MECHANISM OF MOLTEN OXIDE DISCHARGED INTO A SODIUM POOL

Ken-ichi Matsuba, Kenji Kamiyama, Jun-ichi TOYOOKA, Yoshiharu Tobita et autres

To contain the impact of core disruptive accidents (CDAs) of sodium-cooled fast reactors in the reactor vessels, it is important to retain molten core material within the vessel during CDAs. This concept is called in-vessel retention (IVR). Molten core material discharged into …

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Safety Strategy of JSFR to Establish the In-Vessel Retention of the Core Disruptive Accident

Yoshiharu Tobita, Ikken Sato, Kensuke Konishi, Tohru Suzuki et autres

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Experimental studies on the upward fuel discharge for elimination of severe recriticality during core-disruptive accidents in sodium-cooled fast reactors

Kenji Kamiyama, Kensuke Konishi, Ikken Sato, Jun-ichi TOYOOKA et autres

In order to eliminate the energetic potential in the case of postulated core-disruptive accidents (CDAs) of sodium-cooled fast reactors, introduction of a fuel subassembly with an inner-duct structure (FAIDUS) has been considered. Recently, a design option of FAIDUS which leads molten fuel …

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Study on Mechanism of Inner Duct Wall Failure within Fuel Subassembly during Core Disruptive Accidents in an LMFBR Results of Parametric Analyses for Heat Transfer

Jun-ichi TOYOOKA, Hiroshi Endô, Yoshiharu Tobita, Minoru Takahashi

In the design of future sodium-cooled fast reactors, a design measure to prevent severe recriticality events even in the case of core disruptive accidents is considered. This design adopts an inner duct within the fuel subassembly that should allow molten fuel ejection …

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A Study on Mechanism of Early Failure of Inner Duct Wall within Fuel Subassembly with High Heat Flux from Molten Core Materials based on Analysis of an EAGLE Experiment Simulating Core Disruptive Accidents in an LMFBR

Jun-ichi TOYOOKA, Hiroshi Endô, Yoshiharu Tobita, Hisashi Ninokata

In the design of a Japanese sodium-cooled fast reactor (JSFR), a design measure (fuel subassembly with an inner duct structure; FAIDUS) is considered to prevent severe recriticality events even in the case of core disruptive accidents by molten fuel ejection out of …

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Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident

Ikken Sato, Yoshiharu Tobita, Kensuke Konishi, Kenji Kamiyama et autres

In the Japan Sodium Cooled Fast Reactor (JSFR) design, elimination of severe power burst events in the Core Disruptive Accident (CDA) is intended as an effective measure to ensure retention of the core materials within the reactor vessel. The design strategy is …

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Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident

Ikken Sato, Yoshiharu Tobita, Kensuke Konishi, Kenji Kamiyama et autres

In the Japan Sodium Cooled Fast Reactor (JSFR) design, elimination of severe power burst events in the Core Disruptive Accident (CDA) is intended as an effective measure to ensure retention of the core materials within the reactor vessel. The design strategy is …

jp, kz (code pays fourni par la source)