Language：English   Publishing type：Research paper (international conference proceedings)  

Several kinetic models have been proposed to evaluate the aqueous dissolution/ alteration rate of nuclear waste glass for long-term. However, reaction processes controlling the long-term rate are much more subjected to controversy. Temperature dependence of the long-term alteration rate is an essential issue to understand the rate controlling processes. In the present study, the static aqueous alteration tests were performed with a Japanese simulated waste glass P0798 as a function of temperature from 60°C to120°C, and the temperature dependence of the long-term alteration rate was evaluated to understand the rate controlling processes. The tests were performed in 0.001M NaOH solution to maintain a constant solution pH of around 10 during the test period and to provide smectite forming conditions where smectite forms as the major secondary phase without zeolite formation. From the test results on dissolution of boron, the alteration rate at each temperature was analyzed by use of a water-diffusion model. The water-diffusion model used is based on a simple assumption; the glass alteration is controlled by water diffusion with ion-exchange between water (hydronium ion: H3O+) and soluble elements (B, Na, Li, etc) at the glass surface layer with the apparent diffusion coefficient Di. A good agreement was observed between the model analysis and the test results, and the value of Di was evaluated to be 1.2 x 10-22 m2/s at 60°C to 1.8 x 10-21 m2/s at 120°C. The Arrhenius plot of Di showed a good linearity to give the activation energy of 49 kJ/mol, which value is close to that for the residual dissolution rate of French waste glass (53 kJ/mol) by Gin [1], and is very close to that for ion-exchange in sodium aluminosilicate glass (49 kJ/mol) by McGrail [2]. These results suggest that water diffusion with ion-exchange can be the dominant process controlling the alteration rate under smectite forming conditions. At elevated temperatures (100°C and 120°C), however, the model-predicted boron releases deviated from the experimental data at the later stage beyond 50-80 days, which suggests that the alteration layer developing at the glass surface may evolve to be protective against the water diffusion to depress the alteration rate as the alteration proceeds.

Language：English   Publishing type：Research paper (scientific journal)  

Diffusion couples made of dense polycrystalline U1− αPuα− βAmβO2±γ/U1− yPuy− zAmzO2±x oxides were annealed in various thermodynamic conditions (temperature, oxygen partial pressure), and for different durations. The associated actinide redistribution was quantified using Electron Probe Micro-Analysis (EPMA). Average diffusion profiles were obtained from elemental U, Pu, and Am X-ray maps and the resulting interdiffusion coefficients were calculated, then analyzed at the light of our model of point defect chemistry.

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

DOI： DOI: 10.1557/adv.2020.55

Language：English   Publishing type：Research paper (scientific journal)  

DOI： DOI: 10.1299/jsmeicone.2019.27.2095

Language：English   Publishing type：Research paper (scientific journal)  

DOI： DOI: 10.1299/jsmeicone.2019.27.1927

Language：English   Publishing type：Research paper (scientific journal)  

DOI： DOI: 10.1557/adv.2019.81

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

DOI： DOI: 10.1557/adv.2018.184

Language：English   Publishing type：Research paper (scientific journal)  

Language：Japanese   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (scientific journal)  

Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (international conference proceedings)  

Language：English   Publishing type：Research paper (international conference proceedings)  

Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (international conference proceedings)  

Language：English   Publishing type：Research paper (scientific journal)  

The thermal impacts of hull and end piece wastes from high-burn-up UO2 and MOX fuels on a conventional disposal system were investigated.

Language：English   Publishing type：Research paper (international conference proceedings)  

Language：English   Publishing type：Research paper (international conference proceedings)  

Language：English   Publishing type：Research paper (international conference proceedings)  

Static aqueous alteration tests were performed with a Japanese simulated HLW glass, P0798, in the presence of bentonite in order to understand the effects of bentonite on the glass alteration kinetics and on the associated Cs release. Analogous alteration tests were performed in 0.001M NaOH solution without bentonite for comparison. The results indicated that; 1) at the initial stage of alteration up to 50 days, no remarkable difference was observed in the alteration rate between both cases “with” and “without” bentonite, 2) at the later stage beyond 50 days, however, the rate in the case “with” bentonite was larger than that in the case “without” bentonite. These results on the alteration rate were analyzed by use of a water-diffusion model. In the case “without” bentonite, a good agreement was observed between the model analysis and the experimental results at the initial stage of alteration up to 50 days, however, the model analysis deviated from the experimental results at the later stage beyond 50 days. In the case “with” bentonite, on the other hand, a good agreement was observed even at the later stage to give the value of the apparent diffusion coefficient, Di of 3.5x10-21 m2/s. The comparison between both cases suggests that the alteration rate is controlled by the water diffusion in both cases “with” and “without” bentonite, however, the rate is depressed in the case “without” bentonite probably by the protective effects of the alteration layer developing at the glass surface. In the case “with” bentonite, on the other hand, the alteration layer is expected to be less protective. Cesium desorption tests performed for the altered glass and bentonite indicated that most of the cesium dissolved from the glass is retained in the secondary phase of smectite developing in the precipitated layer by sorption with ion-exchange in the case “without” bentonite. In the case “with” bentonite, however, it is likely to be sorbed at bentonite surface.

Language：English   Publishing type：Research paper (scientific journal)  

Aqueous alteration tests were performed with a Japanese simulated waste glass P0798 in alkaline solutions as a function of pH or species/concentration of alkaline metals in the solution in order to evaluate the alteration conditions determining whether smectite (2:1 clay mineral) or analcime (zeolite) forms as the major alteration-phase. XRD analysis of the alteration-phases showed that smectite forms at any pH between 9.5 and 12, and analcime forms at pH above 11, though the formation also depends on species and concentrations of alkaline metals in the solution. These results cannot agree with the thermodynamically predicted phase stability, e.g., smectite is more stable than the thermodynamic prediction shows. On the basis of the results of alteration conditions, the alteration tests were performed under smectite forming conditions, where only smectite forms or no crystalline phases form, in order to evaluate the alteration rate and the mechanism of cesium release/retention. The results showed that the glass alteration proceeds slowly in proportion to square root of time under smectite forming conditions, which indicates that the alteration rate can be controlled by a diffusion process. It was suggested that the alteration rate under smectite forming conditions is independent of the pH, alkaline metal species/ concentration in the solution and whether smectite actually forms or not. The results also indicated that most of cesium dissolved from the glass can be retained in the alteration-phases by reversible sorption onto smectite or irreversible incorporation into analcime, pollucite or solid solutions of them.

Language：Japanese   Publishing type：Research paper (scientific journal)  

Language：English   Publishing type：Research paper (international conference proceedings)  

Language：English   Publishing type：Research paper (international conference proceedings)  

Language：English   Publishing type：Research paper (scientific journal)  

DOI： 10.1016/S0022-3115(01)00588-8

Language：English   Publishing type：Research paper (international conference proceedings)  

Event date： 2022.5

Language：English   Presentation type：Oral presentation (general)  

Country：United States  

Event date： 2022.3 - 2022.6

Language：Japanese   Presentation type：Oral presentation (invited, special)  

Venue：オンライン   Country：Japan  

Event date： 2021.9 - 2021.8

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

高レベルガラス固化体の溶解挙動はガラス組成に加え、pH、地下水組成等の環境条件によって複雑に変化する。本研究では、ガラス試料として国際標準模擬ガラス固化体(ISG)、反応溶液としてSi−29濃縮溶液を用いて、マイクロチャネル流水試験を行うことで、様々なpH条件におけるガラス溶解速度の溶存シリカ濃度依存性を測定・評価した。

Event date： 2021.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：オンライン   Country：Japan  

Event date： 2020.9

Language：Japanese   Presentation type：Oral presentation (general)  

Country：Japan  

Event date： 2019.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：富山大学   Country：Japan  

ガラス固化体の溶解挙動はガラス組成に加え、環境条件（温度, pH, 地下水組成, 反応時間等）によって複雑に変化する。本研究では、国際標準模擬ガラス固化体(ISG)について、反応溶液にSi-29濃縮シリカ溶液を用いてマイクロチャネル流水試験を行い、ガラス溶解速度の溶存シリカ濃度依存性を測定・評価した。

Event date： 2019.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：富山大学   Country：Japan  

福島第一原発の汚染水処理で発生しているCs吸着ゼオライト廃棄物の合理的な処理方法として溶融ガラス固化が挙げられる。本研究ではガラス融剤の種類/添加量、溶融時間等の固化条件をパラメータとしてCs吸着ゼオライトをガラス固化し、ガラス溶融時のCs揮発挙動を速度論的に評価した。

Event date： 2019.4

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：東京工業大学   Country：Japan  

1. 緒言
原子力発電を行うための一連のプロセス全体が「核燃料サイクル」であり，その最終段階に位置する放射性廃棄物の処理・処分のプロセスが「バックエンド」となる．ここでは，バックエンド事業の現状とその進展に必要な研究・開発の課題，更には核燃料サイクルの進展とバックエンドの役割について概説する．
2. 放射性廃棄物の種類・分類
　現在の核燃料サイクルは，燃料となるウランの採鉱に始まり，ウラン濃縮，燃料ペレット製造，原子炉での燃焼と発電を経て使用済燃料の再処理さらには原子力施設の廃止措置（解体）に至る複数のプロセスから成るが，各プロセスでは様々な放射性廃棄物が発生し，その処理と最終処分がサイクルの最終プロセス（バックエンド）となる．これらの放射性廃棄物は，放射能レベル（重量，体積当りの放射能），放射性核種の種類（α・β・γ核種および半減期），性状等によって幾つかの種類に分類される．現在の分類では「高レベル放射性廃棄物」と「低レベル放射性廃棄物」に大別され，このうち「低レベル放射性廃棄物」はさらに「超ウラン核種を含む廃棄物（TRU廃棄物）」「発電所廃棄物（放射能濃度に応じてL1, L2, L3に分類）」「ウラン廃棄物」に分類され，それぞれの特性に応じて処理・処分が行われる．
3. 高レベル放射性廃棄物の処理・処分
　高レベル放射性廃棄物（HLW）は使用済燃料の再処理においてUとPuを回収した後に残る高レベル廃液である．核燃料サイクルからは様々な放射性廃棄物が発生するが，それらの放射能の大半は使用済燃料中の核分裂生成物（FP）やアクチニド（Np, Am, Cm等）に起因するものであり、そのほとんど全てが最終的に高レベル廃液中に移行することから，放射能総量の観点からはHLWが最も重要な対象となる．高レベル廃液は，安全な取り扱い，保管，処分のため化学的に安定なガラス固化体とされ，地上施設で50年程度冷却保管により発熱量を減衰させた後，放射能が充分に減衰するまでの数万年間にわたる確実な隔離・閉じ込めのため地下300m以深の安定な地層中に幾つかの人工バリアを配して埋設処分（地層処分）される．なお，再処理を行わない場合は使用済燃料自身がHLWとなり同様に地層処分（直接処分）される．
4. バックエンド事業と研究・開発
　HLWの地層処分については「特定放射性廃棄物の最終処分に関する法律」成立（2000）の後，実施主体として原子力発電環境整備機構（NUMO）が設立（2000）され，公募方式による処分サイト選定が進められている．地層処分はサイト選定から建設・操業・閉鎖まで100年以上にわたる事業であり，社会的合意を得て実施に至るには，安全性に関する技術情報に加え，事業全体を見通して安全で効率的な処分実現のための基本的考え方や責任体制等を分かり易く示す必要がある．そのため日本全国を対象に処分場所としての科学的な適正可能性を示す「科学的特性マップ」（2017），安全な処分の実現に向けた技術や科学的知見を包括的に示した「包括的技術報告書」（2019予定）等の公開が進められている．一方，研究・開発については，地層処分が物理，化学，材料，地球科学，土木，等の多岐にわたる様々な分野の技術や知見を必要とする事から，それぞれの分野で研究・開発が進められているが，社会的合意を得るには様々な分野の技術や知見を「連携・統合」して処分全体としての正当性と信頼性を示す事も必要であり，連携・統合のための「技術マネジメント」の構築とそれを支える体制の拡充が望まれる．また，低レベル廃棄物や廃止措置との連携・統合，更には核燃料サイクル上流プロセスとの連携・統合をはかり，加えて様々な先端技術を取り込む事でサイクル全体としての真の能力を引き出すバックエンドを確立し、次世代の原子力利用の基盤につなげる事が望まれる．

Event date： 2018.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：岡山大学   Country：Japan  

Event date： 2018.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：岡山大学   Country：Japan  

Event date： 2018.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：岡山大学   Country：Japan  

Event date： 2017.11

Language：English   Presentation type：Oral presentation (general)  

Country：Japan  

Event date： 2017.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：久留米市   Country：Japan  

ガラス固化体の溶解は地下水中のMgとの相互作用により促進または抑制される結果が報告されている。これは生成されるMg含有鉱物の種類が環境条件によって複雑に変化し、ガラス溶解に与える影響も変化するためと考えられる。本研究では、国際標準ガラス（ISG）についてマイクロチャネル流水試験により、pH, Mg濃度をパラメータとした溶解試験を行い、その溶解挙動を評価した。

Event date： 2017.5

Language：English   Presentation type：Oral presentation (general)  

Country：United States  

Event date： 2017.5

Language：English   Presentation type：Oral presentation (general)  

Country：United States  

Event date： 2017.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：東海大学   Country：Japan  

Event date： 2017.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：東海大学   Country：Japan  

Event date： 2016.9

Language：Japanese  

Venue：久留米   Country：Japan  

Event date： 2016.6 - 2017.7

Language：English   Presentation type：Oral presentation (general)  

Country：Japan  

Event date： 2016.3 - 2016.5

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：東北大学   Country：Japan  

福島第一原発事故の汚染水処理で発生したCs吸着ゼオライト廃棄物を安定化処理する方法の一つとして、溶融ガラス固化を検討した。溶融ガラス固化の処理条件が固化体の減容性、Cs固定化率、熱伝導、機械的特性、化学的耐久性等の諸特性に及ぼす影響を定性的、定量的に評価する事を目的とし、諸特性の測定に必要な大きさの固化体試料（40mm x 10mm x 5mm 以上）を作成するとともに、固化体の割れや気泡残留を抑制するための処理条件について検討した。

Event date： 2015.9

Language：Japanese   Presentation type：Oral presentation (general)  

Country：Japan  

マイナーアクチニド分離変換技術の有効性向上のため、技術確立までの期間、再処理高レベル廃棄物を安定かつ再生可能な状態で冷却保管する柔軟な廃棄物管理法の研究開発を実施した。

Event date： 2015.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：茨城大学   Country：Japan  

福島第一原発事故の汚染水処理で発生したCs 吸着ゼオライトを合理的に処理する方法の一つとして、溶融ガラ
ス固化を検討している。本研究では、溶融ガラス固化条件と固化体の諸特性との関係を定量的に評価することを目
的とし、Cs 固定化率の融剤添加量、溶融温度、溶融時間依存性をコールド試験において評価した。また137Cs トレ
ーサーを用いたホット試験も実施し、そのCs 固定化率を評価した。

Event date： 2015.3

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：茨城大学   Country：Japan  

ガラス固化体は、地下水中に存在するMgとの反応によりマグネシウムシリケイトを生成することで、その溶解が促進または抑制される可能性が報告されている。本研究では、マイクロチャネル流水試験法を用いて、マグネシウムシリケイト生成挙動に影響を与えるMg濃度、Si濃度、pH等をパラメータとした溶解試験を行い、我が国の模擬ガラス固化体（P0798ガラス）の溶解挙動に及ぼす影響を評価した。

Event date： 2014.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：京都大学   Country：Japan  

福島第一原発事故の汚染水処理で発生したCs 吸着ゼオライトを合理的に処理する方法の一つとして検討されて
いる溶融ガラス固化では、溶融温度やガラス融剤の添加量などの溶融ガラス固化条件が、減容率やCs 残存率、化
学的耐久性といった固化体の諸特性に影響する。本研究では、ガラス融剤の添加量、溶融温度／時間をパラメータ
として、固化体の組織均一性、Cs 残存率を評価した。

Event date： 2014.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：京都大学   Country：Japan  

我々は新たに開発したマイクロチャネル流水試験法を用いて高レベルガラス固化体溶解挙動の精密な評価を進めている。本研究では、本試験法を用いて我が国の模擬ガラス固化体（P0798）の溶解速度を測定し、その測定精度を評価した。

Event date： 2014.5

Language：English  

Country：Germany  

Event date： 2012.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：広島大学   Country：Japan  

放射性ヨウ素廃棄物処分のための基礎研究として、還元雰囲気における岩石固化体の溶解挙動の評価を目的とし、還元雰囲気において岩石固化体の溶解実験をHS-濃度をパラメーターとして行った。

Event date： 2012.9

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：広島大学   Country：Japan  

我が国の標準模擬ガラス固化体(P0798ガラス)について、残存溶解速度の測定・評価を目的とし、Si飽和またはAl飽和溶液を用い、pHをパラメータとした溶解試験を行なった。

Event date： 2011.12

Presentation type：Oral presentation (general)  

Country：Japan  

Event date： 2011.5

Presentation type：Oral presentation (general)  

Country：United States  

Event date： 2011.1

Country：United Kingdom  

Event date： 2010.9

Venue：北海道大学   Country：Japan  

Event date： 2010.9

Venue：北海道大学   Country：Japan  

Event date： 2010.5

Presentation type：Oral presentation (general)  

Country：United States  

A new type of flow-through test method using micro-reactor was developed and applied to measurement of dissolution kinetics for a Japanese simulated HLW glass, P0798. In this method, a coupon shaped glass is placed on a Teflon plate with a micro-channel (20mm x 2mm x 0.16mm), and a solution is injected into the inlet of the channel at a constant flow rate. The outlet solution, which reacted with glass through the channel, is retrieved to be analyzed for determination of the dissolution rate. By using this method we measured the initial dissolution rate as a function of pH and temperature. The results showed that the initial dissolution rate has “V-shaped” pH dependence at any temp. from 25 to 90°C similar to that for R7T7 glass evaluated by CEA, France. However, a certain difference was observed between them in the temp. dependence at high pHs. Based on the results and comparison, we discussed the dissolution kinetics.

Event date： 2009.9

Presentation type：Oral presentation (general)  

Venue：東北大学   Country：Japan  

Event date： 2009.5

Country：Russian Federation  

We applied a new type of flow-through test method using micro-reactor consisting of a simple test apparatus with compact size to measurement of the dissolution rate of a Japanese type of simulated waste glass (P0798 glass).

Event date： 2008.9

Presentation type：Oral presentation (general)  

Country：Japan  

Event date： 2008.3

Presentation type：Symposium, workshop panel (public)  

Country：Japan  

Event date： 2007.9

Country：Japan  

Presentation type：Symposium, workshop panel (public)  

Country：Belgium  

Several kinetic models have been proposed to predict the aqueous dissolution/ alteration rate of nuclear waste glass for long-term. However, reaction processes controlling the long-term rate are much more subjected to controvert. Temperature dependence of the alteration rate is one of essential issues to be evaluated for an understanding of the rate controlling processes. In the present study, the static alteration tests were performed with a Japanese simulated waste glass P0798 as a function of temperature from 60。C to120。C, and the temperature dependence of the alteration rate was evaluated to understand the rate controlling processes. The tests were performed in 0.001M NaOH solution to maintain a constant solution pH of around 10 during the test period and to provide smectite forming conditions where smectite forms as the major secondary phase without zeolite formation. From the test results on dissolution of boron, the alteration rate at each temperature was analyzed by use of a water-diffusion model. The water-diffusion model used is based on a simple assumption; the glass alteration proceeds being controlled by water diffusion with ion-exchange between water (hydronium ion: H3O+) and soluble elements(B, Na, Li, etc) at the glass surface layer with the apparent diffusion coefficient of Di. A good agreement was observed between the model analysis and the test results, and the value of Di was evaluated to be 1.2 x 10-22 m2/s at 60。C to 1.8 x 10-21 m2/s at 120。C. The Arrhenius plot of Di showed a good linearity to give the activation energy of 49 kJ/mol, which value is much lower than that for the initial dissolution rate of French waste glass(71 kJ/mol) by Delage[1] and Techer[2], but is very close to that for ion-exchange in sodium aluminosilicate glass by McGrail[3]. These results suggest that water diffusion with ion-exchange can be the dominant process controlling the alteration rate under smectite forming conditions. At elevated temperatures(100。C and 120。C), however, the model analysis deviated from the test results, which suggests that the precipitated layer developing at the glass surface can be protective against the diffusion to depress the alteration rate.

Presentation type：Oral presentation (general)  

Country：United States  

Presentation type：Oral presentation (general)  

Venue：名古屋大学   Country：Japan  

Language：Japanese   Presentation type：Oral presentation (general)  

Venue：近畿大学   Country：Japan  

米仏日を中心とするガラス固化体研究国際チームで作製した、組成を単純化した国際標準ガラスについて、マイクロチャネルリアクタ流水溶解試験により、初期溶解速度(ro)のpH／温度依存性を評価した。

Language：Japanese  

Venue：近畿大学   Country：Japan  

ヨウ素廃棄物岩石固化体の地下還元環境における溶解メカニズムの理解を目的とし、(Ar+5%H2）ガス置換グローブボックス中でNa2S水溶液を反応溶液として岩石固化体の溶解実験を行った。

Language：English  

Country：Japan  

Language：English  

Country：Japan  

Type：Peer review 

Number of peer-reviewed articles in foreign language journals：3

Type：Peer review 

Number of peer-reviewed articles in foreign language journals：3

Type：Peer review 

Number of peer-reviewed articles in foreign language journals：5

Type：Peer review 

Number of peer-reviewed articles in foreign language journals：5

Type：Competition, symposium, etc. 

Number of participants：1,000

Type：Competition, symposium, etc. 

Type：Competition, symposium, etc. 

Type：Competition, symposium, etc. 

Number of participants：800

Type：Competition, symposium, etc. 

Number of participants：30

Type：Competition, symposium, etc. 

Number of participants：1,000

Type：Competition, symposium, etc. 

Type：Competition, symposium, etc. 

Number of participants：1,000

Type：Competition, symposium, etc. 

Type：Competition, symposium, etc. 

Number of participants：1,000

Type：Competition, symposium, etc. 

Type：Competition, symposium, etc. 

Type：Competition, symposium, etc. 

Type：Competition, symposium, etc. 

Type：Academic society, research group, etc. 

Type：Competition, symposium, etc. 

Type：Competition, symposium, etc. 

Type：Competition, symposium, etc. 

Number of participants：400

Audience： General,　Scientific,　Company,　Civic organization,　Governmental agency

Type：Research consultation

Audience： General,　Scientific,　Company,　Civic organization,　Governmental agency

Type：Research consultation

Audience： General,　Scientific,　Company,　Civic organization,　Governmental agency

Type：Research consultation

Audience： General,　Scientific,　Company,　Civic organization,　Governmental agency

Type：Research consultation

Audience： Infants,　Schoolchildren,　Junior students,　High school students

Type：Seminar, workshop

Audience： General,　Scientific,　Company,　Civic organization,　Governmental agency

Type：Research consultation

Audience： Infants,　Schoolchildren,　Junior students,　High school students

Type：Seminar, workshop

Audience： General,　Scientific,　Company,　Civic organization,　Governmental agency

Type：Research consultation

日本原子力学会バックエンド部会において「福島除染基礎勉強会」を設立し、福島市において一般市民を対象に勉強会を開催した。（平成24年1月、3月）

Audience： Infants,　Schoolchildren,　Junior students,　High school students

Type：Seminar, workshop

Audience： Infants,　Schoolchildren,　Junior students,　High school students

Type：Seminar, workshop

Audience： Infants,　Schoolchildren,　Junior students,　High school students

Type：Seminar, workshop

Audience： Infants,　Schoolchildren,　Junior students,　High school students

Type：Seminar, workshop