Requirements for Science & Technology in the 21st Century Utilization to Harmonization Industrial Revolution Diversification of resources Mass consump
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1 Simultaneous Satisfaction of Resource Demand and Environmental Protection within the Confines of Assets of Nuclear Fission Reaction
2 Requirements for Science & Technology in the 21st Century Utilization to Harmonization Industrial Revolution Diversification of resources Mass consumption of energy By-Products : NOx, Sox, etc. Global warming by CO 2 emission Turning Point of Fossil Fuel Based Civilization Restricting Unlimited Use of Fossil Resources Ethics based on harmonization Regulation Technical countermeasures Requirements for Future Science & Engineering Will it be a balanced and comprehensive technology? provide new knowledge to the human society develop new fields of science and technology accept and support the civilization harmonize with the environment and society
3 Long Term Prospect for Nuclear Development Advanced Nuclear Science & Technology Self-Consistent Nuclear Energy System Synthesize with Conventional Technology Energy, Material, Information, Technology LWR Radiation Application Fast Reactor Laser, Accelerator Fusion Reactor Chicago Pile (1942) X Ray (1895) Radioactivity (1896) Oklo Natural Reactors (2 billion-years ago)
4 Nuclear Energy System with 5 Objectives satisfied Simultaneously Effective Use of Natural Resources 1.Energy Electric Energy Hydrogen Energy (Efficient use of natural resources) 2.Fuel Fuel production ( Full use of natural resources) Environment Protection Secure Safety & Security (Re-criticality Free Core) 4. Safety Transmutation of Radioactive Waste (Zero-release of radioactive waste) 3. Waste Management 5. No Nuclear Weapon Pu denaturing (Non-proliferation)
5 Future Nuclear Energy System and its Target Energy(electricity or chemical one) Energy Reactor Energy/fuel production and radionuclide transmutation by neutron reaction Neutron balance System Boundary Spent fuel Safety (Elimination of recriticality issues Uranium Fabrication Fuel resources (Fuel recycling) Energy balance Nuclear fuel cycle Long-lived FPs Reprocessing Recovering of recycled material Stable elements No-radioactive waste
6 Energy Balance(Table A) Items Energy (MeV/fission) Produced Energy 1. fission reaction thermal energy Ef Energy loss at power plant energy loss due to conversion Er1 118 Consumed Energy other consumptions Er Energy loss at fuel cycle reprocessing & fabrication Ec1 < 0.2 LLFP nuclide separation Ec2 < 1 LLFP multi-recycling Ec3 < 0.1 Usable Energy 1. Obtained energy electricity Ee 73
7 SCNES neutron balance number of neutrons per fission oxide fuel core metal fuel core Consumption 1. Chain reaction fissile fission fertile fission Breeding (fertile capture) (BR=1.0) FP transumutaion (with isotope separation) Parasitic capture fissile capture others Parent nuclide capture for non-proliferation 0.2 (available) 0.5 (available) Fission yield It is required to achieve non-proliferation by the addition of Np237, Am241 and Am243 to fuel under the condition of the available neutrons.
8 Future Nuclear Energy System needs Fuel Cycle with Isotope Separation A Nuclear Fission generates about 2.9 neutrons - for chain reaction needs 1 neutron - for fuel production needs more than 1 neutron - for transmutation of radioactive FP needs about 0.6 neutron (considering neutron absorption and leakage) Isotope separation below makes it possible FP T 1/2 lower limit(year) Absorption (n/fiss.) Element-wise Separation Isotope-wise Separation
9 Neutron Balance in SCNES with Proliferation Resistance -Pu Grade Target: Reactor Grade Pu- Neutron Reactions Core Fuel Requirement MOX Metal 1. For Chain Reaction N fis1 +N fis2 =1.0 Pu Fissile Fission (N fis1 ) Others Fission (N fis2 ) For Fuel Production (Pu Fissile Production) 238 U, 238 Pu, 240 Pu, capture (N b ) Breeding Ratio = (N b +N p2 )/(N fis1 +N p1 ) For Pu Protection (Taget: Rea. Grade Pu, (Np)) (N p )/N b 0.18 Pu Fisslie, 239, 241 Pu, capture (N p1 ) 237 Np, 241 Am Capture (N p2 ) Reactor Grade Pu or N SFN [n/s/kgpu] 243 Am Capture (N p3 ) Reactor Grade Pu 4. For LLFP Transmutation T 1/2 > 1 year FP Transmutation LLFP capture (N fp ) with isotope separation 5. Others Total Generated Neutron by Fission ) Fundamental Data are delived from Yoichi Fujiie, Masao Suzuki, Nuclear Energy System for a Sustainable Development Perspective -Self-Consistent Nuclear Energy System-, Progress in Nuclear Energy, Vol. 40, No. 3-4, pp , 2002 Re-composed by H. Sagara 2) MA composition data at equilibrium state are delived from A. Mizutani, A. Shono and M. Ishikawa, Investigation of Equilibrium Core by Recycling MA and LLFP in Fast Reactor Cycle(I), JNC TN (1999)
10 Safety of SCNES with Re-criticality Free Reactor Core The safety aspects of a nuclear energy system are discussed sometimes from its inherent safety characteristics. In other words stop, cool and contain. The essential safety measure is to avoid that the radioactive material should have mobility to move outside the system to the environment during meltdown of the core. Especially in fast reactor system, since the criticality issues for both normal and abnormal operation condition are related to the principal safety characteristics of fast reactor core configuration. It means that the core does not show the maximum reactivity configuration related to the material relocation. On the contrary, concerning to the cooling ability of the system it is possible to apply a system with high heat transport material with low pressure operation like sodium cooled system Treatment of HCDA issues like UTOP and ULOF have been made for the safety assessment of FBR in the world even the occurrence probability is negligibly small like 10-7 /(reactor x year). In SCNES we also put our focus on the re-criticality problem. If we consider the low occurrence probability, it is not possible to equip such a system with active element as a safety circuit. We decided to introduce a safety system to make use of physical properties like a melting point and relocation due to phase change in the existence of gravity. a fast reactor system.
11 Objective and outline of EAGLE-project Objective: Confirm that the re-criticality issue would be eliminated from the CDA scenario by the early fuel-discharge from the core region, with clarifying the necessary design conditions for the re-criticality free core. Approach: - Use IGR and Out-of-pile apparatus of the NNC/Kazakhstan Fuel pin Inner duct Example of discharge-enhancing design and discharge phenomena IGR (Impulse Graphite Reactor)
12 表 5 オクロ鉱床の天然原子炉 No.2 跡における核分裂生成物とアクチニドの移動
13 表 6 原子炉の使用済燃料中の核分裂とアクチニド核種 ( 炉から取り出し直度 合計 1 トンあたり )
14 図 7 軽水炉燃料の燃焼前後の組成の変化 (ABWR: 初期ウラン濃縮度 3.7% 平均燃焼度 45,000MWd/t)
15 表 7 50, 100, 1000 年後の放射性廃棄物の放射能比 原子力システム 種類 放射能比 ( 放射性廃棄物の放射能 *1 / 天然ウラン1トンの放射能 *2 50 年後 100 年後 1000 年後 軽水炉 ( ワンススルー ) FP TRU 280,00 82,00 94,00 24, ,00 ウラン + プルトニウムリサイクル型高速炉 FP TRU 280,00 32,00 94,00 14, ,60 アクチニドリサイクル型高速炉 FP TRU *3 280,00 94,00 11 アクチニド + セシウム + ストロンチウムリサイクル型高速炉 FP TRU *3 19,00 12,00 11 アクチニド +7 核種 + セシウム + ストロンチウムリサイクル型高速炉 FP TRU *3 19,00 12, 倍 SCNES 型高速炉 ( アクチニド +30 核種リサイクル型 ) FP TRU *3 *1: 電気出力 100 万 kwe の原子力発電所を 1 年間運転した際に発生する使用済燃料の下記年数経過後の放射能 *2: 天然ウラン 1 トンの放射能として 崩壊系列の娘孫核種を含んだ値 ( ベクレル (4.9 キュリー )) を用いた 娘孫核種を含まない場合の放射能は ベクレル (0.35 キュリー ) となる *3: 超ウラン元素 (TRU) は全てリサイクルされる ( リサイクルロスを 0 と想定 )
16 原子力に期待される役割 : 利用から調和へ ~ 原子力の目指すところ ~ 石炭火力 資源消費量 廃棄物発生量 調和を目的とした科学技術としての原子力 CO 万トン リサイクル 資源を有効利用 し 将来のための 資源を十分に 確保する 原子力の特長 ゼロリリース 廃棄物を 環境中に 放出しない 少ない燃料から大きなエネルギーを取り出せる 発生する廃棄物量が少ない 石油火力 軽水炉ワンススルー プルサーマル 高速増殖炉サイクル 石炭 220 万トン 石油 140 万トン 天然ウラン 170 トン 金属換算 天然ウラン 90 トン 金属換算 天然ウラン 1 トン 金属換算 灰 5 万トン SOx 120 万トン CO 2 SOx 4 万トン 使用済燃料 30 トン 500 万トン ガラス固化体 5 トン ガラス固化体 5 トン 注意 : 電気出力 100 万 kw の発電所を 1 年間運転した場合 図 3 化石燃料と核燃料の量に比較
17 3. 段階的アプローチ 燃料 (U Pu MA) リサイクル (99.99%)+ 全放射性 FP 回収 (99.99%) 核変換 廃棄物放射能は百年で天然ウラン並み SCNES ステップ 2 究極の SCNES ステップ 3 燃料 (U Pu MA) リサイク ル (99.9%)+5LLFP 回収 (99%) 核変換 廃棄物放射能は数百年で天然ウラン並み U+Puリサイクル軽水炉ワンススルー軽水炉 SCNES ステップ1 金属燃料乾式再処理 U+Pu+MAリサイクル U+Puリサイクル燃料 (U Pu MA) リサイク高速炉ル (99.9%)+5LLFP 回収 (99%) 一時保管 U+Pu リサイクル軽水炉 現在の状況 レーザー濃縮技術 ( ステップ 2 と同じ廃棄物放射能削減効果 ) MA: マイナーアクチノイド (Np Am Cm 等の Pu を除く超ウラン元素 ) 5LLFP:5 つの長半減期核分裂生成物 (Tc99, I129, Cs135, Zr93, Sn126) 全放射性 FP: 半減期 1 年以上の核分裂生成物 (28FP)
18 U U-Pu-MA-Zr 高速炉 エネルギー生産 燃料増殖 放射能消滅 炉心崩壊事故の排除 ブランケット無し 燃料製造 使用済燃料 照射後 FP ターゲット FP ターゲット処理 FP ターゲット製造 Zr U, Pu, MA 再処理 I, Tc Cs, Sn (Zr) Cs, Zr, Sn SCNES 副産物 ( 低レベル廃棄物並み ) FP 同位体のレーザー分離 図 5 SCNES の全体システム
19 図 8 放射性廃棄物の放射性毒性の経年変化
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Presentation title (on one or two lines)
PSN Number: PSNN-2014-0979 Document Number: AFT-2014-000353 Rev.000(1) 金属燃料高速炉による放射性廃棄物 の消滅処理 国際シンポジウム 放射性廃棄物低減に向けた現状と将来の展望 ~ ゼロリリースを目指して ~ 於 : 東京 タワーホール船堀 有江和夫 ( 株 ) 東芝電力システム社原子力開発設計部 担当部長 2014 年 10 月
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開催日時 平成25年11月14日 木 9:3 17: 会場 東海大学高輪キャンパス1号館 第2会議室 講師 東海大学工学部原子力工学科 教授 大江 俊昭 氏 講義 課題1 放射性廃棄物処分の安全評価解析の基礎 Ⅰ 浅地中ピット処分の事例分析 Ⅱ 地層処分の事例分析 課題2 放射性廃棄物処分の安全評価
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本レポートは独立行政法人日本原子力研究開発機構が不定期に発行する成果報告書です 本レポートの入手並びに著作権利用に関するお問い合わせは 下記あてにお問い合わせ下さい なお 本レポートの全文は日本原子力研究開発機構ホームページ (http://www.jaea.go.jp) より発信されています 独立行政法人日本原子力研究開発機構研究技術情報部研究技術情報課 319-1195 茨城県那珂郡東海村白方白根
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