Portions of this study have been previously published in the Journal of Radioanalytical and Nuclear Chemistry.3,13 A patent is pending for this method.

注意：ここで説明するプロセスは、放射性物質の使用（例えば、ウラン六水和物）と、いくつかの腐食性物質を含んでいます。適切な防護服や機器は、サンプル調製中（白衣、手袋、眼の保護、およびヒュームフードを含む）を使用する必要があります。また、この作業に使用実験室面積は放射能汚染のために定期的に監視する必要があります。 注：必要に応じて化学化合物を 、表1に記載されているこの製剤は、先に検討することによって開発されたトリニタイトための組成データを報告し、ここで報告された10質量分率は、いくつかの異なるトリニタイトサンプルの質量分率を平均することによって決定された10 &quot;欠落&quot;塊。 （画分が1に合計しないように）燃料、タンパーを追加する際にある程度の柔軟性を可能にするために存在し、他の成分。いくつかのトリニタイトサンプルの我々の独立した分析は、石英のみ鉱物相であることを示唆していますトリニタイトで生存する。5そこで、石英は、当社の標準トリニタイト製剤（STF）に含まれる唯一の鉱物です。他の鉱物の遺物粒がトリニタイトで報告されているが、11これらは例外ではなく、ルールになる傾向があります。一般的には、石英、溶融ガラスに見られる唯一の鉱物である。10,12また、石英砂は、都市核溶融ガラスの形成に重要となるアスファルトやコンクリートの一般的な構成要素です。 <table fo:keep-together.within-page="1"><tbody><tr height="41"><td colspan="2" height="41" style="height:42px;width:317px;"> 平均化トリニタイトデータ </td><td colspan="2" style="width:317px;"> 標準トリニタイト製剤（STF） </td></tr><tr height="22"><td height="22" style="height:22px;width:159px;"> 化合物 </td><td style="width:159px;"> 質量分率 </td><td style="width:159px;"> 化合物 </td><html><td style="width:159px;"> 質量分率 </td></tr><tr height="26"><td height="26" style="height:26px;width:159px;"> SiO 2 </td><td style="width:159px;"> 6.42x10 -1 </td><td style="width:159px;"> SiO 2 </td><td style="width:159px;"> 6.42x10 -1 </td></tr><tr height="26"><td height="26" style="height:26px;width:159px;"> Al 2 O 3 </td><td style="width:159px;"> 1.43x10 -1 </td><td style="width:159px;"> Al 2 O 3 </td><td style="width:159px;"> 1.43x10 -1 </td></tr><tr height="25"><td height="25" style="height:25px;width:159px;"> CaO </td><td style="width:159px;"> 9.64x10 -2 </td><td style="width:159px;"> CaO </td><td style="width:159px;"> 9.64x10 -2 </td></tr><tr height="25"><td height="25" style="height:25px;width:159px;"> FeO </td><td style="width:159px;"> 1.97x10 -2 </td><html> &quot;&gt;のFeO </td><td style="width:159px;"> 1.97x10 -2 </td></tr><tr height="25"><td height="25" style="height:25px;width:159px;"> MgOの</td><td style="width:159px;"> 1.15x10 -2 </td><td style="width:159px;"> MgOの</td><td style="width:159px;"> 1.15x10 -2 </td></tr><tr height="26"><td height="26" style="height:26px;width:159px;"> Na 2 Oを</td><td style="width:159px;"> 1.25x10 -2 </td><td style="width:159px;"> Na 2 Oを</td><td style="width:159px;"> 1.25x10 -2 </td></tr><tr height="26"><td height="26" style="height:26px;width:159px;"> K 2 O </td><td style="width:159px;"> 5.13x10 -2 </td><td style="width:159px;"> KOH </td><td style="width:159px;"> 6.12x10 -2 </td></tr><tr height="25"><td height="25" style="height:25px;width:159px;"> MnO </td><td style="width:159px;"> 5.05x10 -4 </td><td style="width:159px;"> MnO </td>9px; &quot;&gt; 5.05x10 -4 </td></tr><tr height="26"><td height="26" style="height:26px;width:159px;"> TiO 2の</td><td style="width:159px;"> 4.27x10 -3 </td><td style="width:159px;"> TiO 2の</td><td style="width:159px;"> 4.27x10 -3 </td></tr><tr height="25"><td height="25" style="height:25px;width:159px;">トータル</td><td style="width:159px;"> 9.81x10 -1 </td><td style="width:159px;">トータル</td><td style="width:159px;"> 9.91x10 -1 </td></tr></tbody></table>化合物の表1。リスト。 STFの調製注意：必要な機器は、マイクロバランス、金属ヘラ、セラミック乳鉢と乳棒、化学ヒュームフード、ゴム手袋、白衣、および眼の保護が含まれています。 <ol><li>非放射性成分の混合<ol><li>石英砂の少なくとも65グラム（SiO 2）ではAl 2 O 3を15gを取得&lt;/サブ&gt;粉末、酸化カルシウム粉末10g、のFeO粉末2g、MgO粉末2gを、Na 2 Oを粉末2g、KOHペレット7gの、酸化マンガン粉末1g及びTiO 2粉末1g（ 表1に列挙した化合物）。 </li><li> 表1に記載されているように正確に、各化合物の質量分率を測定するために、微量天秤と小さなへらを使用してください。最良の結果を一度に非放射性前駆体マトリックスの100グラムを準備するために。 </li><li> （〜10〜20ミクロンのサイズの顆粒に）粉砕する乳鉢と乳棒を使用して、徹底的に化合物を混合し、SiO 2を64.2グラムを含む均質な粉末混合物を形成する、 の Al 2 O 3、CaOを、1.97グラムの9.64グラムの14.2グラムFeO、MgOを1.15グラム、のNa 2 Oを 1.25グラムのKOHの6.12グラム、のMnOの0.0505グラム、及びTiO 2の0.427グラム。 </li><li>次のステップが取られる直前に、ボールミキサーを使用して、混合物を撹拌します。 </li></ol></li><li>ウラン六水和物（UNH）とSTFの混合<ol><li> AcquUNHの少なくとも1gをIRE。 </li><li>ヒュームフードの内側には、1〜2μmで顆粒の微粉末を形成する（乳鉢と乳棒を使用して）いくつかのUNH結晶を粉砕。 </li><li> （この比率は1キロトンの収率で単純な武器をシミュレートするために適切である）非放射性前駆体マトリックスのグラム当たりUNHの33.75μgのを追加します。13 </li><li>乳鉢と乳棒を用いて、UNH含む、粉末混合物を混ぜます。溶融工程の直前に最終混合を完了します。 </li></ol></li></ol> 1グラムメルトガラスサンプルの2生産注意：必要な機器は、1,600℃以上、高純度黒鉛ルツボ、長いステンレス製るつぼトング、耐熱手袋、眼の保護定格HTFが含まれています。炉からサンプルを導入するか、削除する際に耐熱手袋と目の保護を着用してください。彼らは炉からのまぶしさを軽減としてティント安全ゴーグル（または太陽メガネ）が便利です。 <ol><li>非放射性サンプルの製造<ol><li>純粋な石英砂の〜100gで（例えばモルタルなど）の厚さのセラミックの皿を記入し、試料が溶融される炉の場所の近くに、室温で維持します。 </li><li> 1,500℃に予熱HTF。 </li><li>慎重に非放射性粉末混合物の1.00グラムを測定し、高純度の黒鉛坩堝に粉末を配置します。 </li><li>慎重に（鋼るつぼトングの長い対を用いて）加熱HTFでるつぼを配置し、30分間混合物を溶融します。 </li><li> （再びトングを使用して）サンプルを削除し、砂を充填したモルタルへの溶融サンプルを注ぎます。 </li><li>ガラスビーズを取り扱​​う前に1〜2分間冷却してください。 </li><li> （必要な場合）の残留砂を除去するために、ビーズを磨きます。 </li></ol></li><li>放射性試料の作製<ol><li>繰り返しは、上記の2.1.1と2.1.2手順。 </li><li>慎重に（UNH含む）放射性粉末混合物の1.00グラムを測定し、powdを配置<html>相互汚染を避けるために、別個のへらと天秤を用いて高純度黒鉛坩堝におけるER。 </li><li>上記2.1.6 - を繰り返し2.1.4手順。 </li><li>放射能汚染をチェックする（手持ち放射線検出器および/またはスワイプアッセイを用いて）炉の周囲の領域を監視します。 </li></ol></li></ol> 3.サンプルのアクティベーション注：下記の式は、兵器級（濃縮）ウラン金属の使用を想定して誘導しました。 UNHまたは酸化ウランの量は、元素のウランの質量分率と235 U濃縮のレベルに応じてスケーリングする必要があります。 <ol><li>ウラン笛でメルトガラス試料の活性化<ol><li> （mは Uウラン質量分率を表し、Yは、武器の収率を示す）13以下の式を使用して、サンプルに必要なウラン金属の質量分率を計算します。 473 / 53473eq1.jpg &quot;/&gt; </li><li>オプション：以下の式を使用して、タンパ（例えば、天然ウラン、鉛、タングステン）の質量分率を計算します。13 <img alt="式（2）" src="/files/ftp_upload/53473/53473eq2.jpg" /></li><li> M sはグラムでのサンプルの質量を表し、N fは照射の間、サンプルにおいて生成さ核分裂の数を表し、以下の式13を用いて試料中の核分裂の目標数を計算します。 <img alt="式3" src="/files/ftp_upload/53473/53473eq3.jpg" /></li><li> M 235が 235 Uの質量分率（濃縮レベル）を表し、Tの IRRは、秒単位の照射時間である13以下の式を使用して、必要な照射時間を計算します。 <img alt="式（4）" src="/files/ftp_upload/53473/53473eq4.jpg" /></li><li>以下のためのサンプルを照射4.0×10 14 N / cmで2 /秒の熱中性子束にIRR秒のt。例えば、（35の共振比が熱を持つ）HFIRで気送管1（PT-1）で60秒照射はUNHの870μgの410μgのに（等価を含む試料では約1.1×10 11核分裂が生成されます天然ウラン、または235 Uの3.0μgの）。これは、0.1キロトンの収率で武器によって生成溶融ガラスサンプルをシミュレートするように設計された1つ0.433グラムのガラスビーズのために達成されています。この試料を十分にクックらによって分析された。14 </li><li>放射性試料照射後の処理に適用される安全なプロトコルに従ってください。 </li></ol></li><li>プルトニウム燃料（計画要因）とメルトガラス試料の活性化<ol><li> 13 ここで、m プルトニウム represen以下の式を使用して、サンプルに必要なプルトニウム金属の質量分率を計算しますプルトニウム質量分率TS と Y は、武器の収量を表しています。 <img alt="式（5）" src="/files/ftp_upload/53473/53473eq5.jpg" /></li><li>手順を繰り返し上記の3.1.2と3.1.3。 </li><li>溶融ガラス試料中の核分裂の所望の数を得るために必要な照射時間を決定します。この時間は、組成やグ​​レードプルトニウムだけでなく、中性子エネルギースペクトルに依存します。 </li></ol></li></ol>注意：必要とされるプルトニウム、追加の分析を扱うときに細心の注意を払うべきです。この記事の執筆時点では、唯一のウランは、合成溶融ガラス試料UTで生産し、HFIRで照射に使用されています。

<ol>
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This work was performed under grant number DE-NA0001983 from the Stewardship Science Academic Alliances (SSAA) Program of the National Nuclear Security Administration (NNSA).

ステップ1.2.2と1.2.3に関する注意：UNHの正確な量は、シミュレートされるシナリオによって異なります。 Giminaro らによって開発された計画の式は、このペーパーの「サンプル活性化」の項で説明したように、与えられたサンプル13のためのウランの適切な量を選択するために使用することができます。また、酸化ウラン（UO 2またはU 3 O 8）が利用可能な?...

Concerns over the potential malicious use of nuclear weapons by terrorists or rogue nations have highlighted the importance of nuclear forensics analysis for the purpose of attribution.1 Rapid post-detonation analysis techniques are desirable to shorten the attribution timeline as much as possible. The development and validation of such techniques requires realistic nuclear debris samples for testing. Nuclear testing no longer occurs in the United States and nuclear surface debris from the testing era is not readily available (with the exception of trinitite - the melt glass produced by the first nuclear test at the trinity site) and therefore realistic surrogate debris is needed. 
The primary goal of the method described here is the production of realistic surrogate nuclear debris similar to trinitite. Synthetic nuclear melt glass samples which are readily available to the academic community can be used to test existing analysis techniques and to develop new methods such as thermo-chromatography for rapid post-detonation analysis.2 With this goal in mind the current study is focused on producing samples which mimic trinitite but do not contain any sensitive weapon design information. The fuel and tamper components within these samples are completely generic and the comparison to trinitite is based on chemistry, morphology, and physical characteristics. The similarities between trinitite and the synthetic nuclear melt glass produced in this study have been previously discussed.3
The purpose of this article is to outline the details of the production process used at the University of Tennessee (UT). This production process was developed with two key parameters in mind: 1) the composition of material incorporated into nuclear melt glass, and 2) the melting temperature of the material. Methods exist for estimating the melting temperature of glass forming networks4 and these techniques have been employed here, along with additional experimentation to determine the optimal processing temperature for the trinitite matrix.5
Alternative methods for surrogate debris production have been published recently. The use of high power lasers has the advantage of creating sufficiently high temperatures to cause elemental fractionation within the target matrix.6 Porous chromatographic substrates have been used to produce small particles similar to fallout particles using condensed phase methods7. The latter method is most useful for producing particulate debris (nuclear fallout) and has been demonstrated with natural metals. The advantages of the method presented here are 1) simplicity, 2) reproducibility, and 3) scalability (sample sizes can range from tiny beads to large chunks of melt glass). Also, this method is expandable both in terms of production output and variety of explosive scenarios covered, and it has already been demonstrated using radioactive materials. A sample has been successfully activated at the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). Natural uranium compounds were added to the matrix prior to melting and fission products were produced in situ by neutron irradiation. 
Methods within the glass making industry and those employed for the purpose of radioactive waste immobilization8 have been consulted in the development of the method presented here. The unique effects of radiation in glasses are of inherent interest9 and will constitute an important area of study as this method is further developed. 
The method described below is appropriate for any application where a bulk melt glass sample is desired. These samples most closely resemble the material found near the epicenter of a nuclear explosion. Samples of various sizes can be produced, however, methods employing plasma torches or lasers will be more useful for simulating fine particulate debris. Also, commercial HTFs do not reach temperatures high enough to cause elemental fractionation for a wide range of elements. This method should be employed when physical and morphological characteristics are of primary importance.

<table border="0" cellpadding="0" cellspacing="0" width="1019">
	<tbody>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">High Temperature Furnace (HTF)</td>
			<td style="width:200px;">Carbolite</td>
			<td style="width:119px;">HTF 18</td>
			<td style="width:469px;">1800C HTF used to melt samples</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">High Temperature Drop Furnace</td>
			<td style="width:200px;">CM Inc.</td>
			<td style="width:119px;">1706 BL</td>
			<td>1700C Drop Furnace used to melt samples</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">Graphite Crucibles</td>
			<td style="width:200px;">SCP Science</td>
			<td style="width:119px;">040-060-041</td>
			<td>27 mL high purity graphite crucibles (10 pack)</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">Crucible Tongs</td>
			<td style="width:200px;">Grainger</td>
			<td style="width:119px;">5ZPV0</td>
			<td>26 in, stainless steele tongs for handling crucibles</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">Heat Resistent Gloves</td>
			<td style="width:200px;">Grainger</td>
			<td style="width:119px;">8814-09</td>
			<td>Gloves used to protect hands from heat during sample intro/removal</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">Mortar &#38; Pestle</td>
			<td style="width:200px;">Fisherbrand</td>
			<td style="width:119px;">S337631</td>
			<td>300 mL, Ceramic mortar and pestle for powdering and mixing</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">Micro Balance</td>
			<td style="width:200px;">Grainger</td>
			<td style="width:119px;">8NJG2</td>
			<td>220g Cap, high precision scale for measuring powder mass</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">Spatulas</td>
			<td style="width:200px;">Fisherbrand</td>
			<td style="width:119px;">14374</td>
			<td>Metal spatulas for measure small quantities of powder</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">SiO2</td>
			<td style="width:200px;">Sigma-Aldrich</td>
			<td style="width:119px;">274739-5KG</td>
			<td>Quartz Sand&#160; CAS Number: 14808-60-7</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">Al2O3</td>
			<td style="width:200px;">Sigma-Aldrich</td>
			<td style="width:119px;">11028-1KG</td>
			<td>Aluminum Oxide Powder&#160; CAS Number: 1344-28-1</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">CaO</td>
			<td style="width:200px;">Sigma-Aldrich</td>
			<td style="width:119px;">12047-2.5KG</td>
			<td>Calcium Oxide Powder&#160; CAS Number: 1305-78-8</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">FeO</td>
			<td style="width:200px;">Sigma-Aldrich</td>
			<td style="width:119px;">400866-25G</td>
			<td>Iron Oxide Powder&#160; CAS Number: 1345-25-1</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">MgO</td>
			<td style="width:200px;">Sigma-Aldrich</td>
			<td style="width:119px;">342793-250G</td>
			<td>Magnesium Oxide Powder&#160; CAS Number: 1309-48-4</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">Na2O</td>
			<td style="width:200px;">Sigma-Aldrich</td>
			<td style="width:119px;">36712-25G</td>
			<td>Sodium Oxide Powder&#160; CAS Number: 1313-59-3</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;">KOH</td>
			<td style="width:200px;">Sigma-Aldrich</td>
			<td style="width:119px;">278904-250G</td>
			<td>Potasium Hydroxide Pellets&#160; CAS Number: 12030-88-5</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">MnO</td>
			<td style="width:200px;">Sigma-Aldrich</td>
			<td style="width:119px;">377201-500G</td>
			<td>Manganese Oxide Powder&#160; CAS Number: 1344-43-0</td>
		</tr>
		<tr height="26">
			<td height="26" style="height:27px;width:231px;">TiO2</td>
			<td style="width:200px;">Sigma-Aldrich</td>
			<td style="width:119px;">791326-5G</td>
			<td>Titanium Oxide Beads&#160; CAS Number: 12188-41-9</td>
		</tr>
	</tbody>
</table>

production of synthetic nuclear melt glass

Realistic surrogate nuclear debris is needed within the nuclear forensics community to test and validate post-detonation analysis techniques. Here we outline a novel process for producing bulk surface debris using a high temperature furnace. The material developed in this study is physically and chemically similar to trinitite (the melt glass produced by the first nuclear test). This synthetic nuclear melt glass is assumed to be similar to the vitrified material produced near the epicenter (ground zero) of any surface nuclear detonation in a desert environment. The process outlined here can be applied to produce other types of nuclear melt glass including that likely to be formed in an urban environment. This can be accomplished by simply modifying the precursor matrix to which this production process is applied. The melt glass produced in this study has been analyzed and compared to trinitite, revealing a comparable crystalline morphology, physical structure, void fraction, and chemical composition.

本研究で生産非放射性サンプルはトリニタイトに比べて1〜3は、物理的特性および形態が実際に類似していることを示しますされている。 図1は、巨視的レベルで観察された色と質感の類似性を明らかに写真を提供します。 図2は、ミクロンレベルでの類似の特徴を明らかに走査型電子顕微鏡（SEM）二次電子（SE）画像を示します。 SEM分析は?...

Watch this Scientific Journal Video about Production of Synthetic Nuclear Melt Glass at JoVE.com

Production of Synthetic Nuclear Melt Glass

A protocol for the production of synthetic nuclear melt glass, similar to trinitite, is presented.

合成核メルトガラスの製造

Realistic surrogate nuclear debris is needed within the nuclear forensics community to test and validate post-detonation analysis techniques. Here we ...

production-of-synthetic-nuclear-melt-glass

Research

JoVE Journal

Engineering

9.4K ビュー.  United States Military Academy. A protocol for the production of synthetic nuclear melt glass, similar to trinitite, is presented.

ビデオ: Production of Synthetic Nuclear Melt Glass

Ambient Method for the Production of an Ionically Gated Carbon Nanotube Common Cathode in Tandem Organic Solar Cells

A method of fabricating organic photovoltaic (OPV) tandems that requires no vacuum processing is presented. These devices are comprised of two solution-processed polymeric cells connected in parallel by a transparent carbon nanotubes (CNT) interlayer. This structure includes improvements in fabrication techniques for tandem OPV devices. First the need for ambient-processed cathodes is considered. The CNT anode in the tandem device is tuned via ionic gating to become a common cathode. Ionic gating employs electric double layer charging to lower the work function of the CNT electrode. Secondly, the difficulty of sequentially stacking tandem layers by solution-processing is addressed. The devices are fabricated via solution and dry-lamination in ambient conditions with parallel processing steps. The method of fabricating the individual polymeric cells, the steps needed to laminate them together with a common CNT cathode, and then provide some representative results are described. These results demonstrate ionic gating of the CNT electrode to create a common cathode and addition of current and efficiency as a result of the lamination procedure.

A method of fabricating, in ambient conditions, organic photovoltaic tandem devices in a parallel configuration is presented. These devices feature an air-processed, semi-transparent, carbon nanotube common cathode.

タンデム有機太陽電池におけるイオン的ゲーテッドカーボンナノチューブ共通カソードの生産のための周囲の方法

A method of fabricating organic photovoltaic (OPV) tandems that requires no vacuum processing is presented. These devices are comprised of two ...

工学

Quantification of Hydrogen Concentrations in Surface and Interface Layers and Bulk Materials through Depth Profiling with Nuclear Reaction Analysis

Nuclear reaction analysis (NRA) via the resonant 1H(15N,&#945;&#947;)12C reaction is a highly effective method of depth profiling that quantitatively and non-destructively reveals the hydrogen density distribution at surfaces, at interfaces, and in the volume of solid materials with high depth resolution. The technique applies a 15N ion beam of 6.385 MeV provided by an electrostatic accelerator and specifically detects the 1H isotope in depths up to about 2 &#956;m from the target surface. Surface H coverages are measured with a sensitivity in the order of ~1013 cm-2 (~1% of a typical atomic monolayer density) and H volume concentrations with a detection limit of ~1018 cm-3 (~100 at. ppm). The near-surface depth resolution is 2-5 nm for surface-normal 15N ion incidence onto the target and can be enhanced to values below 1 nm for very flat targets by adopting a surface-grazing incidence geometry. The method is versatile and readily applied to any high vacuum compatible homogeneous material with a smooth surface (no pores). Electrically conductive targets usually tolerate the ion beam irradiation with negligible degradation. Hydrogen quantitation and correct depth analysis require knowledge of the elementary composition (besides hydrogen) and mass density of the target material. Especially in combination with ultra-high vacuum methods for in-situ target preparation and characterization, 1H(15N,&#945;&#947;)12C NRA is ideally suited for hydrogen analysis at atomically controlled surfaces and nanostructured interfaces. We exemplarily demonstrate here the application of 15N NRA at the MALT Tandem accelerator facility of the University of Tokyo to (1) quantitatively measure the surface coverage and the bulk concentration of hydrogen in the near-surface region of a H2 exposed Pd(110) single crystal, and (2) to determine the depth location and layer density of hydrogen near the interfaces of thin SiO2 films on Si(100).

We illustrate the application of 1H(15N,&#945;&#947;)12C resonant nuclear reaction analysis (NRA) to quantitatively evaluate the density of hydrogen atoms on the surface, in the volume, and at an interfacial layer of solid materials. The near-surface hydrogen depth profiling of a Pd(110) single crystal and of SiO2/Si(100) stacks is described.

核反応分析と深さ方向分析を通じて表面・界面層とバルク材料中の水素濃度の定量

Nuclear reaction analysis (NRA) via the resonant 1H(15N,&#945;&#947;)12C reaction is a highly effective method of depth profiling that quantitatively and ...

Electrospray Deposition of Uniform Thickness Ge23Sb7S70 and As40S60 Chalcogenide Glass Films

Solution-based electrospray film deposition, which is compatible with continuous, roll-to-roll processing, is applied to chalcogenide glasses. Two chalcogenide compositions are demonstrated: Ge23Sb7S70 and As40S60, which have both been studied extensively for planar mid-infrared (mid-IR) microphotonic devices. In this approach, uniform thickness films are fabricated through the use of computer numerical controlled (CNC) motion. Chalcogenide glass (ChG) is written over the substrate by a single nozzle along a serpentine path. Films were subjected to a series of heat treatments between 100 &#176;C and 200 &#176;C under vacuum to drive off residual solvent and densify the films. Based on transmission Fourier transform infrared (FTIR) spectroscopy and surface roughness measurements, both compositions were found to be suitable for the fabrication of planar devices operating in the mid-IR region. Residual solvent removal was found to be much quicker for the As40S60 film as compared to Ge23Sb7S70. Based on the advantages of electrospray, direct printing of a gradient refractive index (GRIN) mid-IR transparent coating is envisioned, given the difference in refractive index of the two compositions in this study.

Electrospray Deposition of Uniform Thickness Ge23Sb7S70 and As40S60 Chalcogenide Glass Films

A method of uniform thickness solution-derived chalcogenide glass film deposition is demonstrated using computer numerical controlled motion of a single-nozzle electrospray.

均一な厚さのGeのエレクトロスプレーデポジション<sub&gt; 23</sub&gt; Sbの<sub&gt; 7</sub&gt; S<sub&gt; 70</sub&gt;と同様に<sub&gt; 40</sub&gt; S<sub&gt; 60</sub&gt;カルコゲナイドガラスフィルム

Solution-based electrospray film deposition, which is compatible with continuous, roll-to-roll processing, is applied to chalcogenide glasses. Two ...

Applying X-ray Imaging Crystal Spectroscopy for Use as a High Temperature Plasma Diagnostic

X-ray spectra provide a wealth of information on high temperature plasmas; for example electron temperature and density can be inferred from line intensity ratios. By using a Johann spectrometer viewing the plasma, it is possible to construct profiles of plasma parameters such as density, temperature, and velocity with good spatial and time resolution. However, benchmarking atomic code modeling of X-ray spectra obtained from well-diagnosed laboratory plasmas is important to justify use of such spectra to determine plasma parameters when other independent diagnostics are not available. This manuscript presents the operation of the High Resolution X-ray Crystal Imaging Spectrometer with Spatial Resolution (HIREXSR), a high wavelength resolution spatially imaging X-ray spectrometer used to view hydrogen- and helium-like ions of medium atomic number elements in a tokamak plasma. In addition, this manuscript covers a laser blow-off system that can introduce such ions to the plasma with precise timing to allow for perturbative studies of transport in the plasma.

X-ray spectra provide a wealth of information on high temperature plasmas. This manuscript presents the operation of a high wavelength resolution spatially imaging X-ray spectrometer used to view hydrogen- and helium-like ions of medium atomic number elements in a tokamak plasma.

高温プラズマ診断として使用するためのX線イメージングクリスタル分光法を適用します

X-ray spectra provide a wealth of information on high temperature plasmas; for example electron temperature and density can be inferred from line ...

Indoor Experimental Assessment of the Efficiency and Irradiance Spot of the Achromatic Doublet on Glass (ADG) Fresnel Lens for Concentrating Photovoltaics

We present a method to characterize achromatic Fresnel lenses for photovoltaic applications. The achromatic doublet on glass (ADG) Fresnel lens is composed of two materials, a plastic and an elastomer, whose dispersion characteristics (refractive index variation with wavelength) are different. We first designed the lens geometry and then used ray-tracing simulation, based on the Monte Carlo method, to analyze its performance from the point of view of both optical efficiency and the maximum attainable concentration. Afterwards, ADG Fresnel lens prototypes were manufactured using a simple and reliable method. It consists of a prior injection of plastic parts and a consecutive lamination, together with the elastomer and a glass substrate to fabricate the parquet of ADG Fresnel lenses. The accuracy of the manufactured lens profile is examined using an optical microscope while its optical performance is evaluated using a solar simulator for concentrator photovoltaic systems. The simulator is composed of a xenon flash lamp whose emitted light is reflected by a parabolic mirror. The collimated light has a spectral distribution and an angular aperture similar to the real Sun. We were able to assess the optical performance of the ADG Fresnel lenses by taking photographs of the irradiance spot cast by the lens using a charge-coupled device (CCD) camera and measuring the photocurrent generated by several types of multi junction (MJ) solar cells, which have been previously characterized at a solar simulator for concentrator solar cells. These measurements have demonstrated the achromatic behavior of ADG Fresnel lenses and, as a consequence, the suitability of the modelling and manufacturing methods.

Indoor Experimental Assessment of the Efficiency and Irradiance Spot of the Achromatic Doublet on Glass ADG Fresnel Lens for Concentrating Photovoltaics

The achromatic doublet on glass (ADG) Fresnel lens makes use of two materials with differing dispersion to reduce chromatic aberration and increase attainable concentration. In this paper, a protocol for the complete characterization of the ADG Fresnel lens is presented.

効率と集中太陽光発電用ガラス (ADG) フレネル レンズの色消しの放射照度場所の屋内の実験的評価

We present a method to characterize achromatic Fresnel lenses for photovoltaic applications. The achromatic doublet on glass (ADG) Fresnel lens is ...

The Modular Design and Production of an Intelligent Robot Based on a Closed-Loop Control Strategy

Intelligent robots are part of a new generation of robots that are able to sense the surrounding environment, plan their own actions and eventually reach their targets. In recent years, reliance upon robots in both daily life and industry has increased. The protocol proposed in this paper describes the design and production of a handling robot with an intelligent search algorithm and an autonomous identification function.
First, the various working modules are mechanically assembled to complete the construction of the work platform and the installation of the robotic manipulator. Then, we design a closed-loop control system and a four-quadrant motor control strategy, with the aid of debugging software, as well as set steering gear identity (ID), baud rate and other working parameters to ensure that the robot achieves the desired dynamic performance and low energy consumption. Next, we debug the sensor to achieve multi-sensor fusion to accurately acquire environmental information. Finally, we implement the relevant algorithm, which can recognize the success of the robot&#39;s function for a given application.
The advantage of this approach is its reliability and flexibility, as the users can develop a variety of hardware construction programs and utilize the comprehensive debugger to implement an intelligent control strategy. This allows users to set personalized requirements based on their needs with high efficiency and robustness.

We present a protocol on modular design and production of intelligent robots to help scientific and technical workers design intelligent robots with special production tasks based on personal needs and individualized design.

モジュラー設計と閉ループ制御戦略に基づく知能ロボットの生産

Intelligent robots are part of a new generation of robots that are able to sense the surrounding environment, plan their own actions and eventually reach ...

Production and Characterization of Vacuum Deposited Organic Light Emitting Diodes

A method for producing simple and efficient thermally-activated delayed fluorescence organic light-emitting diodes (OLEDs) based on guest-host or exciplex donor-acceptor emitters is presented. With a step-by-step procedure, readers will be able to repeat and produce OLED devices based on simple organic emitters. A patterning procedure allowing the creation of personalized indium tin oxide (ITO) shape is shown. This is followed by the evaporation of all layers, encapsulation and characterization of each individual device. The end goal is to present a procedure that will give the opportunity to repeat the information presented in cited publication but also using different compounds and structures in order to prepare efficient OLEDs.

A protocol for the production of simple structured organic light-emitting diodes (OLEDs) is presented.

真空の作製と解析堆積有機発光ダイオード

A method for producing simple and efficient thermally-activated delayed fluorescence organic light-emitting diodes (OLEDs) based on guest-host or exciplex ...

Methods of Ex Situ and In Situ Investigations of Structural Transformations: The Case of Crystallization of Metallic Glasses

We demonstrate the use of two nuclear-based analytical methods that can follow the modifications of microstructural arrangement of iron-based metallic glasses (MGs). Despite their amorphous nature, the identification of hyperfine interactions unveils faint structural modifications. For this purpose, we have employed two techniques that utilize nuclear resonance among nuclear levels of a stable 57Fe isotope, namely M&#246;ssbauer spectrometry and nuclear forward scattering (NFS) of synchrotron radiation. The effects of heat treatment upon (Fe2.85Co1)77Mo8Cu1B14 MG are discussed using the results of ex situ and in situ experiments, respectively. As both methods are sensitive to hyperfine interactions, information on structural arrangement as well as on magnetic microstructure is readily available. M&#246;ssbauer spectrometry performed ex situ describes how the structural arrangement and magnetic microstructure appears at room temperature after the annealing under certain conditions (temperature, time), and thus this technique inspects steady states. On the other hand, NFS data are recorded in situ during dynamically changing temperature and NFS examines transient states. The use of both techniques provides complementary information. In general, they can be applied to any suitable system in which it is important to know its steady state but also transient states.

Methods of Ex Situ and In Situ Investigations of Structural Transformations: The Case of Crystallization of Metallic Glasses

Here, we present a protocol to describe ex situ and in situ investigations of structural transformations in metallic glasses. We employed nuclear-based analytical methods which inspect hyperfine interactions. We demonstrate the applicability of M&#246;ssbauer spectrometry and nuclear forward scattering of synchrotron radiation during temperature-driven experiments.

Ex その場その場で調査構造変換の方法: 金属ガラスの結晶化の事例

We demonstrate the use of two nuclear-based analytical methods that can follow the modifications of microstructural arrangement of iron-based metallic ...

Optimized Sealing Process and Real-Time Monitoring of Glass-to-Metal Seal Structures

Residual stress is an essential factor to keeping the hermeticity and robustness of a glass-to-metal seal structure. The purpose of this report is to demonstrate a novel protocol to characterize and measure residual stress in a glass-to-metal seal structure without destroying the insulation and hermeticity of sealing materials. In this research, a femto-laser inscribed fiber Bragg grating sensor is used. The glass-to-metal seal structure that is measured consists of a metal shell, sealing glass, and Kovar conductor. To make the measurements worthwhile, the specific heat treatment of metal-to-glass seal (MTGS) structure is explored to obtain the model with best hermeticity. Then, the FBG sensor is embedded into the path of sealing glass and becomes well-fused with the glass as the temperature cools to RT. The Bragg wavelength of FBG shifts with the residual stress generated in sealing the glass. To calculate the residual stress, the relationship between Bragg wavelength shift and strain is applied, and the finite element method is also used to make the results reliable. The online monitoring experiments of residual stress in sealing glass are carried out at different loads, such as high temperature and high pressure, to broaden functions of this protocol in harsh environments.

Key procedures to optimize the sealing process and achieve real-time monitoring of the metal-to-glass seal (MTGS) structure are described in detail. The embedded fiber Bragg grating (FBG) sensor is designed to achieve online monitoring of temperature and high-level residual stress in the MTGS with simultaneous environmental pressure monitoring.

ガラスから金属へのシール構造の最適化されたシールプロセスとリアルタイムモニタリング

Residual stress is an essential factor to keeping the hermeticity and robustness of a glass-to-metal seal structure. The purpose of this report is to ...

Production of a Strain-Measuring Device with an Improved 3D Printer

A traditional strain measurement sensor needs to be electrified and is susceptible to electromagnetic interference. In order to solve the fluctuations in the analog electrical signal in a traditional strain gauge operation, a new strain measurement method is presented here. It uses a photographic technique to display the strain change by amplifying the change of the pointer displacement of the mechanism. A visual polydimethylsiloxane (PDMS) lens with a focal length of 7.16 mm was added to a smartphone camera to generate a lens group acting as a microscope to capture images. It had an equivalent focal length of 5.74 mm. Acrylonitrile butadiene styrene (ABS) and nylon amplifiers were used to test the influence of different materials on the sensor performance. The production of the amplifiers and PDMS lens is based on improved 3D printing technology. The data obtained were compared with the results from finite element analysis (FEA) to verify their validity. The sensitivity of the ABS amplifier was 36.03 &plusmn; 1.34 &#181;&epsilon;/&#181;m, and the sensitivity of the nylon amplifier was 36.55 &plusmn; 0.53 &#181;&epsilon;/&#181;m.

This work presents a strain measurement sensor consisting of an amplification mechanism and a polydimethylsiloxane microscope manufactured using an improved 3D printer.

改良された3Dプリンターを用いた歪み測定装置の製造

A traditional strain measurement sensor needs to be electrified and is susceptible to electromagnetic interference. In order to solve the fluctuations in ...