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.

Dikkat: Burada özetlenen süreç radyoaktif madde kullanımını içerir (örneğin, Uranyum nitrat hegzahidrat) ve çeşitli korozif maddeler. Uygun koruyucu giysi ve ekipmanları numune hazırlama sırasında (bir laboratuvar önlüğü, eldiven, koruyucu gözlük ve davlumbaz dahil) kullanılmalıdır. Buna ek olarak, bu iş için kullanılan laboratuvar alanları radyoaktif kirlenme açısından düzenli olarak izlenmelidir. Not:. Gerekli kimyasal bileşikler Tablo 1&#39;de listelenmiştir Bu formülasyon trinitite için önceden inceleyerek kompozisyon verileri rapor geliştirilen belirlendi burada bildirilen 10 kütle fraksiyonları farklı trinitite örnekleri için kitle kesirler ortalayarak 10 &quot;kayıp&quot; kitle.. (fraksiyonlar birlik toplamı değil) yakıt, sabotaj ve diğer bileşenleri eklerken bazı esneklik sağlamak için vardır. Birkaç trinitite örneklerin Bağımsız analiz kuvars sadece mineral fazı olduğunu düşündürmektedirtrinitite hayatta kalma. 5. Bu nedenle, kuvars bizim Standart Trinitite Formülasyon (STF) dahil tek bir mineraldir. Diğer minerallerin kalıntı taneleri trinitite bildirilmiş olmakla birlikte, bu durum 11 yerine, bir kural olma eğilimindedir. Genel olarak, kuvars cam eriyik bulunan tek bir mineraldir. 10,12 Ayrıca, kuvars kumu, kentsel bir nükleer erimiş cam oluşumunda önemli olacaktır asfalt ve betonun bir sık rastlanan bir bileşenidir. <table fo:keep-together.within-page="1"><tbody><tr height="41"><td colspan="2" height="41" style="height:42px;width:317px;"> Ortalamalı Trinitite Veri </td><td colspan="2" style="width:317px;"> Standart Trinitite Formülasyon (STF) </td></tr><tr height="22"><td height="22" style="height:22px;width:159px;"> Bileşik </td><td style="width:159px;"> Kütle Fraksiyon </td><td style="width:159px;"> Bileşik </td><html><td style="width:159px;"> Kütle Fraksiyon </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; FeO </td><td style="width:159px;"> 1.97x10 -2 </td></tr><tr height="25"><td height="25" style="height:25px;width:159px;"> MgO </td><td style="width:159px;"> 1.15x10 -2 </td><td style="width:159px;"> MgO </td><td style="width:159px;"> 1.15x10 -2 </td></tr><tr height="26"><td height="26" style="height:26px;width:159px;"> Na 2 O </td><td style="width:159px;"> 1.25x10 -2 </td><td style="width:159px;"> Na 2 O </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;"> TiO2 </td><td style="width:159px;"> 4.27x10 -3 </td><td style="width:159px;"> TiO2 </td><td style="width:159px;"> 4.27x10 -3 </td></tr><tr height="25"><td height="25" style="height:25px;width:159px;"> Toplam </td><td style="width:159px;"> 9.81x10 -1 </td><td style="width:159px;"> Toplam </td><td style="width:159px;"> 9.91x10 -1 </td></tr></tbody></table> Kimyasal bileşiklerin Tablo 1.. Listesi. STF 1. Hazırlık Not: Gerekli Ekipmanlar bir mikroterazi, metal spatula, bir seramik havan, bir kimyasal davlumbaz, lateks eldiven, bir laboratuvar önlüğü ve göz koruması içerir. <ol><li> Radyoaktif olmayan bileşenlerin karıştırılması <ol><li> Kuvars kumu en az 65 g (SiO 2), Al 2 O 3 15 g Edinme &lt;/ sub&gt; tozu, CaO tozu 10 g, FeO tozu 2 g, MgO tozu 2 g, Na 2 O toz 2 g KOH peletleri 7 g, MnO tozu 1 g TiO2 tozu (1 g Tablo 1&#39;de listelenen bileşikler). </li><li> Tablo 1 &#39;de gösterildiği gibi, her bir bileşiğin hassas kütle fraksiyonlarını ölçmek için bir mikro terazi ve küçük bir spatula kullanın. En iyi sonuçlar, aynı anda radyoaktif olmayan ön-madde matrisinin 100 g hazırlanması için. </li><li> SiO 2 64.2 g, Al 2 O 3 14.2 g CaO 9.64 g, 1.97 g ihtiva eden bir homojen toz karışımı oluşturan bileşikler iyice karıştırın (~ 10-20 um boyutu granüller) toz haline ve bir havan ve havan tokmağı kullanarak FeO, MgO 1.15 g, Na 2 O. 1.25 g KOH 6.12 g, MnO 0,0505 g ve TiO2 0,427 gr. </li><li> Bir sonraki adım alınır kısa bir süre önce, bir top mikser kullanılarak, karışımın çalkalayın. </li></ol></li><li> Uranyum nitrat heksahidrat ile STF Karıştırma (UNH) <ol><li> AcquUNH ire en az 1 gr. </li><li> Bir çeker ocak içinde, 1-2 um granüllerin ince bir toz oluşturmak için (bir havan ve havan tokmağı kullanılarak) bir kaç UNH kristaller toz haline. </li><li> Radyoaktif olmayan ön-madde matrisinin gramı başına UNH bölgesinin 33.75 ug ekleyin (bu oran 1 Kiloton bir verimle basit bir silah simüle etmek için uygun olan). 13 </li><li> İyice bir havan ve havan tokmağı kullanılarak, UNH de dahil olmak üzere, toz karışımı karıştırılır. Kısa bir süre eritme adımından önce son karıştırma tamamlayın. </li></ol></li></ol> 1-gram Erime Cam Örneğinin 2. Üretim Not: Gerekli Ekipmanlar 1.600 ° C veya daha yüksek, yüksek saflıkta grafit potalar, uzun paslanmaz çelik pota maşa, ısıya dayanıklı eldivenler ve göz koruması nominal bir HTF içerir. Tanıtan veya fırından örnekleri sökerken ısıya dayanıklı eldiven ve koruyucu gözlük takılmalıdır. Onlar fırından parlamayı azaltmak olarak Renkli güvenlik gözlükleri (ya da güneş gözlüğü) yararlıdır. <ol><li> Radyoaktif olmayan bir örnek üretimi <ol><li> Saf kuvars kumu ~ 100 g ile kalın seramik tabak (örneğin bir harç gibi) doldurun ve numuneler erimiş olacak fırının yerin yakınında oda sıcaklığında muhafaza. </li><li> 1500 ° C&#39;ye HTF önceden ısıtın. </li><li> Dikkatle olmayan radyoaktif toz karışımı 1.00 g ölçmek ve yüksek saflıkta grafit pota tozu yerleştirin. </li><li> Dikkatle (çelik pota maşa uzun çifti kullanılarak) ısıtıldı HTF Kroze yerleştirin ve 30 dakika için karışımın eriyik. </li><li> (Yine maşa kullanarak) numuneyi çıkarın ve kum dolu harcın içine erimiş numune dökün. </li><li> Cam boncuk tutmadan önce 1-2 dakika soğumasını bekleyin. </li><li> (Gerekirse) bakiye kum çıkarmak için boncuk parlatmak. </li></ol></li><li> Radyoaktif bir madde üretimi <ol><li> Tekrarlayın yukarıda 2.1.1 ve 2.1.2 numaralı adımları. </li><li> Dikkatle (UNH dahil) radyoaktif toz karışımı 1.00 gram ölçmek ve powd yerleştirmek<html> Çapraz bulaşmayı önlemek için ayrı bir spatula ve mikrobalans kullanılarak yüksek saflıkta grafit potada er. </li><li> Yukarıdaki 2.1.6 - 2.1.4 tekrarlayın adımları. </li><li> Radyoaktif kirlenme kontrol etmek için (bir el radyasyon dedektörü ve / veya tokatlamak analizleri kullanılarak) fırının çevresini izleyin. </li></ol></li></ol> 3. Numune Aktivasyon Not: aşağıdaki denklemler silah notu (zenginleştirilmiş) uranyum metalinin kullanımını varsayılarak elde edilmiştir. UNH veya Uranyum Oksit miktarları element uranyum kütle oranı ve 235 U zenginleştirme derecesine göre ölçekli gerekecektir. <ol><li> Uranyum Fue ile Erime Cam Numune aktivasyonu <ol><li> (M U uranyum kütlesi fraksiyonu temsil eder ve Y silah verimi gösterir) 13 altında eşitlik kullanılarak numune için gerekli olan uranyum metal kütle fraksiyonu hesaplayın: 473 / 53473eq1.jpg &quot;/&gt; </li><li> İsteğe bağlı: Aşağıdaki denklem kullanılarak sabotaj (örneğin, doğal uranyum, kurşun, tungsten) kütle fraksiyonu hesaplayın: 13 <img alt="Denklem 2" src="/files/ftp_upload/53473/53473eq2.jpg" /></li><li> Ms gram olarak örnek kütlesini temsil eder ve N f ışınlama sırasında numunesinde üretilen fissions sayısını temsil eder ve aşağıdaki denklem 13 kullanılarak numunedeki fissions hedef sayısını hesaplayın: <img alt="Denklem 3" src="/files/ftp_upload/53473/53473eq3.jpg" /></li><li> M 235 235 U kütle fraksiyonu (zenginleştirme seviyesini temsil eder) ve t irr saniye ışınlama zamanı 13&#39;ün altında denklem kullanılarak gerekli ışınlama süresini hesaplayın: <img alt="Denklem 4" src="/files/ftp_upload/53473/53473eq4.jpg" /></li><li> Için numune ışın tedavisi4.0 x 10 14 n / cm2 / sn kadar bir termal nötron akısı az irr saniye t. Örneğin, (35 termal rezonansa oranı ile) HFIR de pnömatik Tüp 1 (PT-1) ve 60 sn ışınlama 870 UNH ug (eşdeğer 410 ug içeren bir numunede, yaklaşık 1.1 x 10 11 fissions üretecek Doğal uranyum veya 235 U 3.0 ug). Bu 0,1 kiloton verimle bir silah tarafından üretilen bir erime örneği ile simüle etmek için dizayn edilmiş bir 0.433 g cam boncuk için gerçekleştirilmiştir. Bu örnek iyice Cook ve arkadaşları tarafından analiz edilmiştir. 14 </li><li> Radyoaktif örnek sonrası radyoterapi işlemek için yürürlükteki güvenlik protokollerini takip edin. </li></ol></li><li> Plütonyum Yakıt ile Erime Cam Numune aktivasyonu (Planlama Faktörler) <ol><li> Pu Represen m, 13 aşağıdaki denklem kullanılarak numune için gereken plütonyum metal kütle fraksiyonu hesaplayınPlütonyum kütle oranı ts ve Y silah verimi temsil: <img alt="Denklem 5" src="/files/ftp_upload/53473/53473eq5.jpg" /></li><li> Tekrarlayın Adımlar yukarıda 3.1.2 ve 3.1.3. </li><li> Eriyik cam numunedeki fissions istenilen sayıda elde etmek için gerekli ışınlama süresi belirler. Bu sefer kompozisyonu ve sınıf plütonyum gibi nötron enerji spektrumunun bağlıdır. </li></ol></li></ol> Not: gerekli olacak plütonyum ve ek analiz ile uğraşırken Büyük bir dikkatle alınmalıdır. Bu yazı gibi, sadece uranyum sentetik eriyik cam örneklerinin UT üretilen ve HFIR ışınlanmış kullanılır olmuştur.

<ol>
	<li>Carnesdale, A. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=.">.</a> Nuclear Forensics: A Capability at Risk (Abbreviated Version). , (2010).</li><li>Garrison, J. R., Hanson, D. E., Hall, H. L. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Monte+Carlo+analysis+of+thermochromatography+as+a+fast+separation+method+for+nuclear+forensics.">Monte Carlo analysis of thermochromatography as a fast separation method for nuclear forensics.</a> J Radioanal Nucl Chem. 291 (3), 885-894 (2011).</li><li>Molgaard, J. J., et al. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Development+of+synthetic+nuclear+melt+glass+for+forensic+analysis.">Development of synthetic nuclear melt glass for forensic analysis.</a> J Radioanal Nucl Chem. 304 (3), 1293-1301 (2015).</li><li>Fluegel, A. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Modeling+of+Glass+Liquidus+Temperatures+using+Disconnected+Peak+Functions.">Modeling of Glass Liquidus Temperatures using Disconnected Peak Functions.</a> , (2007).</li><li>Oldham, C. J., Molgaard, J. J., Auxier, J. D., Hall, H. L. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Comparison+of+Nuclear+Debris+Surrogates+Using+Powder+X-Ray+Diffraction.">Comparison of Nuclear Debris Surrogates Using Powder X-Ray Diffraction.</a> , (2014).</li><li>Liezers, M., Fahey, A. J., Carman, A. J., Eiden, G. C. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=The+formation+of+trinitite-like+surrogate+nuclear+explosion+debris+(+SNED+)+and+extreme+thermal+fractionation+of+SRM-612+glass+induced+by+high+power+CW+CO+2+laser+irradiation.">The formation of trinitite-like surrogate nuclear explosion debris ( SNED ) and extreme thermal fractionation of SRM-612 glass induced by high power CW CO 2 laser irradiation.</a> J Radional Nucl Chem. 304 (2), 705-715 (2015).</li><li>Harvey, S. D., et al. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Porous+chromatographic+materials+as+substrates+for+preparing+synthetic+nuclear+explosion+debris+particles.">Porous chromatographic materials as substrates for preparing synthetic nuclear explosion debris particles.</a> J Radioanal Nucl Chem. 298 (3), 1885-1898 (2013).</li><li>Hanni, J. B., et al. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Liquidus+temperature+measurements+for+modeling+oxide+glass+systems+relevant+to+nuclear+waste+vitrification.">Liquidus temperature measurements for modeling oxide glass systems relevant to nuclear waste vitrification.</a> J Mater Res. 20 (12), 3346-3357 (2005).</li><li>Weber, W. J., et al. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Radiation+Effects+in+Glasses+Used+for+Immobilization+of+High-Level+Waste+and+Plutonium+Disposition.">Radiation Effects in Glasses Used for Immobilization of High-Level Waste and Plutonium Disposition.</a> J Mater Res. 12 (8), 1946-1978 (1997).</li><li>Eby, N., Hermes, R., Charnley, N., Smoliga, J. A. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Trinitite-the+atomic+rock.">Trinitite-the atomic rock.</a> Geol Today. 26 (5), 180-185 (2010).</li><li>Bellucci, J. J., Simonetti, A. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Nuclear+forensics:+searching+for+nuclear+device+debris+in+trinitite-hosted+inclusions.">Nuclear forensics: searching for nuclear device debris in trinitite-hosted inclusions.</a> J Radioanal Nucl Chem. 293 (1), 313-319 (2012).</li><li>Ross, C. S. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=.">.</a> Optical Properties of Glass from Alamogordo, New Mexico. , (1948).</li><li>Giminaro, A. V., et al. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Compositional+planning+for+development+of+synthetic+urban+nuclear+melt+glass.">Compositional planning for development of synthetic urban nuclear melt glass.</a> J Radional Nucl Chem. , (2015).</li><li>Cook, M. T., Auxier, J. D., Giminaro, A. V., Molgaard, J. J., Knowles, J. R., Hall, H. L. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=A+comparison+of+gamma+spectra+from+trinitite+versus+irradiated+synthetic+nuclear+melt+glass.">A comparison of gamma spectra from trinitite versus irradiated synthetic nuclear melt glass.</a> J Radioanal Nucl Chem. , (2015).</li><li>Fahey, J., Zeissler, C. J., Newbury, D. E., Davis, J., Lindstrom, R. M. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Postdetonation+nuclear+debris+for+attribution.">Postdetonation nuclear debris for attribution.</a> Proc Natl Acad Sci U S A. 107 (47), 20207-20212 (2010).</li><li>Bellucci, J. J., Simonetti, A., Koeman, E. C., Wallace, C., Burns, P. C. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=A+detailed+geochemical+investigation+of+post-nuclear+detonation+trinitite+glass+at+high+spatial+resolution:+Delineating+anthropogenic+vs.+natural+components.">A detailed geochemical investigation of post-nuclear detonation trinitite glass at high spatial resolution: Delineating anthropogenic vs. natural components.</a> Chem Geol. 365, 69-86 (2014).</li><li>Donohue, P. H., Simonetti, A., Koeman, E. C., Mana, S., Peter, C. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Nuclear+Forensic+Applications+Involving+High+Spatial+Resolution+Analysis+of+Trinitite+Cross-Sections.">Nuclear Forensic Applications Involving High Spatial Resolution Analysis of Trinitite Cross-Sections.</a> J Radioanal Nucl Chem. , (2015).</li><li>Eaton, G. F., Smith, D. K. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=Aged+nuclear+explosive+melt+glass:+Radiography+and+scanning+electron+microscope+analyses+documenting+radionuclide+distribution+and+glass+alteration.">Aged nuclear explosive melt glass: Radiography and scanning electron microscope analyses documenting radionuclide distribution and glass alteration.</a> J Radioanal Nucl Chem. 248 (3), 543-547 (2001).</li><li>Kersting, A. B., Smith, D. K. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=.">.</a> Observations of Nuclear Explosive Melt Glass Textures and Surface Areas. , (2006).</li><li>. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=.">.</a> IAEA Safeguards Glossary. , (2001).</li><li>Glasstone, S., Dolan, P. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=.">.</a> Effects of Nuclear Weapons. , (1977).</li><li>Carney, K. P., Finck, M. R., McGrath, C. A., Martin, L. R., Lewis, R. R. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=The+development+of+radioactive+glass+surrogates+for+fallout+debris.">The development of radioactive glass surrogates for fallout debris.</a> J Radioanal Nucl Chem. 299 (1), 363-372 (2013).</li><li>Molgaard, J. J., Auxier, J. D., Hall, H. L. <a target="_blank" href="http://www.ncbi.nlm.nih.gov/entrez/query.fcgi?db=PubMed&cmd=Search&doptcmdl=Citation&defaultField=Title+Word&term=A+Comparison+of+Activation+Products+in+Different+Types+of+Urban+Nuclear+Melt+Glass.">A Comparison of Activation Products in Different Types of Urban Nuclear Melt Glass.</a> , (2015).</li></ol>

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

Adımlarla 1.2.2 ve 1.2.3 ilişkin Not: UNH tam miktarı senaryoya bağlı olarak değişecektir simüle ediliyor. Giminaro ve ark. Geliştirilirken formülleri, bu kağıt &quot;Örnek aktivasyonu&quot; bölümünde açıklandığı gibi, belirli bir örnek 13 için uranyum uygun kütleye seçmek için kullanılabilir. Ayrıca, uranyum oksit (UO 2 ya da U 3 O 8) varsa, UNH yerine kullanılır ve (UNH ya uranyum oksit olsun) dikkate alınması gereken bir bileşikte <...

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><tbody><tr><td>High Temperature Furnace (HTF)</td><td>Carbolite</td><td>HTF 18</td><td>1,800 &amp;#176;C HTF used to melt samples</td></tr><tr><td>High Temperature Drop Furnace</td><td>CM Inc.</td><td>1706 BL</td><td>1,700 &amp;#176;C Drop Furnace used to melt samples</td></tr><tr><td>Graphite Crucibles</td><td>SCP Science</td><td>040-060-041</td><td>27 ml high purity graphite crucibles (10 pack)</td></tr><tr><td>Crucible Tongs</td><td>Grainger</td><td>5ZPV0</td><td>26 in., stainless steele tongs for handling crucibles</td></tr><tr><td>Heat Resistent Gloves</td><td>Grainger</td><td>8814-09</td><td>Gloves used to protect hands from heat during sample intro/removal</td></tr><tr><td>Mortar &amp;amp; Pestle</td><td>Fisherbrand</td><td>S337631</td><td>300 ml, Ceramic mortar and pestle for powdering and mixing</td></tr><tr><td>Micro Balance</td><td>Grainger</td><td>8NJG2</td><td>220 g Cap, high precision scale for measuring powder mass</td></tr><tr><td>Spatulas</td><td>Fisherbrand</td><td>14374</td><td>Metal spatulas for measure small quantities of powder</td></tr><tr><td>SiO&lt;sub&gt;2&lt;/sub&gt;</td><td>Sigma-Aldrich</td><td>274739-5KG</td><td>Quartz Sand&amp;nbsp; CAS Number: 14808-60-7</td></tr><tr><td>Al&lt;sub&gt;2&lt;/sub&gt;O&lt;sub&gt;3&lt;/sub&gt;</td><td>Sigma-Aldrich</td><td>11028-1KG</td><td>Aluminum Oxide Powder&amp;nbsp; CAS Number: 1344-28-1</td></tr><tr><td>CaO</td><td>Sigma-Aldrich</td><td>12047-2.5KG</td><td>Calcium Oxide Powder&amp;nbsp; CAS Number: 1305-78-8</td></tr><tr><td>FeO</td><td>Sigma-Aldrich</td><td>400866-25G</td><td>Iron Oxide Powder&amp;nbsp; CAS Number: 1345-25-1</td></tr><tr><td>MgO</td><td>Sigma-Aldrich</td><td>342793-250G</td><td>Magnesium Oxide Powder&amp;nbsp; CAS Number: 1309-48-4</td></tr><tr><td>Na&lt;sub&gt;2&lt;/sub&gt;O</td><td>Sigma-Aldrich</td><td>36712-25G</td><td>Sodium Oxide Powder&amp;nbsp; CAS Number: 1313-59-3</td></tr><tr><td>KOH</td><td>Sigma-Aldrich</td><td>278904-250G</td><td>Potasium Hydroxide Pellets&amp;nbsp; CAS Number: 12030-88-5</td></tr><tr><td>MnO</td><td>Sigma-Aldrich</td><td>377201-500G</td><td>Manganese Oxide Powder&amp;nbsp; CAS Number: 1344-43-0</td></tr><tr><td>TiO&lt;sub&gt;2&lt;/sub&gt;</td><td>Sigma-Aldrich</td><td>791326-5G</td><td>Titanium Oxide Beads&amp;nbsp; 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.

Bu çalışmada üretilen radyoaktif olmayan numuneler trinitite göre ve 1-3 fiziksel özellikleri ve morfolojisi gerçekten benzer olduğunu göstermektedir Rakamlar oylandı. 1 makroskopik düzeyde gözlenen renk ve doku benzerlikler ortaya fotoğrafları sağlar Şekil. Şekil 2 mikron seviyesinde benzer özellikler ortaya Taramalı Elektron Mikroskobu (SEM) İkincil Elektron (SE) görüntüleri gösterir. SEM analizi, bir SEM ve SE...

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.

Sentetik Nükleer Erime Cam Üretimi

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

Video: Production of Synthetic Nuclear Melt Glass

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 Situ ve yapısal dönüşümleri in Situ soruşturma yöntemleri: Metalik gözlük kristalleşme olgusu

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

Mühendislik

Molten-Salt Synthesis of Complex Metal Oxide Nanoparticles

The development of feasible synthesis methods is critical for the successful exploration of novel properties and potential applications of nanomaterials. Here, we introduce the molten-salt synthesis (MSS) method for making metal oxide nanomaterials. Advantages over other methods include its simplicity, greenness, reliability, scalability, and generalizability. Using pyrochlore lanthanum hafnium oxide (La2Hf2O7) as a representative, we describe the MSS protocol for the successful synthesis of complex metal oxide nanoparticles (NPs). Furthermore, this method has the unique ability to produce NPs with different material features by changing various synthesis parameters such as pH, temperature, duration, and post-annealing. By fine-tuning these parameters, we are able to synthesize highly uniform, non-agglomerated, and highly crystalline NPs. As a specific example, we vary the particle size of the La2Hf2O7&#160;NPs by changing the concentration of the ammonium hydroxide solution used in the MSS process, which allows us to further explore the effect of particle size on various properties. It is expected that the MSS method will become a more popular synthesis method for nanomaterials and more widely employed in the nanoscience and nanotechnology community in the upcoming years.

Here, we demonstrate a unique, relatively low-temperature, molten-salt synthesis method for preparing uniform complex metal oxide lanthanum hafnate nanoparticles.

Karmaşık Metal Oksit nano tanecikleri erimiş tuz sentezi

The development of feasible synthesis methods is critical for the successful exploration of novel properties and potential applications of nanomaterials. ...

Kimya

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.

Camdan Metale Sızdırmazlık Yapılarının Optimize Edilmiş Sızdırmazlık Süreci ve Gerçek Zamanlı İzlemesi

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 ...

Comparison of Two Different Synthesis Methods of Single Crystals of Superconducting Uranium Ditelluride

Single crystal specimens of the actinide compound uranium ditelluride, UTe2, are of great importance to the study and characterization of its dramatic unconventional superconductivity, believed to entail spin-triplet electron pairing. A variety in the superconducting properties of UTe2 reported in the literature indicates that discrepancies between synthesis methods yield crystals with different superconducting properties, including the absence of superconductivity entirely. This protocol describes a process to synthesize crystals that exhibit superconductivity via chemical vapor transport, which has consistently exhibited a superconducting critical temperature of 1.6 K and a double transition indicative of a multi-component order parameter. This is compared to a second protocol that is used to synthesize crystals via the molten metal flux growth technique, which produces samples that are not bulk superconductors. Differences in the crystal properties are revealed through a comparison of structural, chemical, and electronic property measurements, showing that the most dramatic disparity occurs in the low-temperature electrical resistance of the samples.

Here, we present a protocol to synthesize two types of UTe2 crystals: those exhibiting robust superconductivity, via chemical vapor transport synthesis, and those lacking superconductivity, via molten metal flux synthesis.

Süper İletken Uranyum Ditellüridin Tek Kristallerinin İki Farklı Sentez Yönteminin Karşılaştırılması

Single crystal specimens of the actinide compound uranium ditelluride, UTe2, are of great importance to the study and characterization of its dramatic ...

Kalıcı Lüminesan Nanopartiküllerin Hidrotermal Sentezi

Synthesis of Persistent Luminescent Nanoparticles for Rewritable Displays and Illumination Applications

Persistent luminescent nanoparticles (PLNPs) possess the capabilities to maintain extended longevity and robust emission even after the excitation has ceased. PLNPs have been widely used across various domains, including information displays, data encryption, biological imaging, and artistic decoration with sustained and vivid luminosity, providing boundless possibilities for a variety of innovative technology and artistic projects. This protocol focuses on an experimental procedure for the hydrothermal synthesis of PLNPs. The successful synthesis of enduring luminescent nanomaterials with Mn2+ or Cr3+ serving as a luminescent center in Zn2GeO4: Mn (ZGO: Mn) or ZnGa2O4: Cr highlights the universality of this synthetic method. On the other hand, the optical properties of ZGO: Mn can be changed by adjusting the pH of precursor solutions, demonstrating the tunability of the protocol. When charged with ultraviolet (UV) at a wavelength of 365 nm for 3 min and then stopped, PLNPs exhibit the remarkable capacity to generate afterglow efficiently and consistently, which makes them ideal for making two-dimensional rewritable displays and three-dimensional transparent, luminous artworks. This protocol outlined in this paper provides a feasible method for the synthesis of persistent luminescent nanoparticles for further illumination and imaging applications, opening up novel prospects for the fields of science and art.

Yazar Spotlight: Fonksiyonel Nanomalzemelerle Biyogörüntüleme ve Tedaviyi Geliştirme

A protocol is presented for the synthesis of persistent luminescent nanomaterials (PLNPs) and their potential applications in rewritable displays and artistic processing utilizing the afterglow effect under ultraviolet light (365 nm) irradiation.

Yeniden Yazılabilir Ekranlar ve Aydınlatma Uygulamaları için Kalıcı Lüminesan Nanopartiküllerin Sentezi

Persistent luminescent nanoparticles (PLNPs) possess the capabilities to maintain extended longevity and robust emission even after the excitation has ...

Fluid-cell Raman Spectroscopy for operando Studies of Reaction and Transport Phenomena during Silicate Glass Corrosion

Fluid-cell Raman Spectroscopy (FCRS) enables the real-time and space-resolved (operando) study of reaction mechanisms, kinetics, and their mutual interactions with transport processes during silicate glass corrosion at the micrometer scale and at elevated temperatures. This manuscript provides a detailed protocol for setting up an FCRS experiment, exemplified by a corrosion experiment with a ternary Na borosilicate glass and a 0.5 M NaHCO3 solution at a temperature of 86 &#177; 1 &#176;C. The protocol involves (i) sample preparation, (ii) assembly of the fluid cell, and (iii) setting of Raman measurement parameters for collecting Raman spectra across the sample/solution interface in regular time intervals. The results from the experiment show the formation of a water-rich zone between a silica-based surface alteration layer (SAL) and the pristine glass, which is an intrinsic feature of an interface-coupled dissolution-precipitation model for the formation of a SAL during silicate glass corrosion. The ability to track the reaction and transport processes during the corrosion of silicate glasses and potentially of other transparent materials, spatially resolved and in real-time, represents a unique strength of this technique, overcoming the disadvantages of conventional analysis of multi-step quenching experiments. The corrosion of the top side of the glass sample represents a current issue, reducing spatial resolution at depth due to precipitation within the laser pathway. This is caused by a solution-filled gap between the sapphire window of the fluid cell lid and the top side of the monolith, which is difficult to avoid during the experimental setup. This must be taken into account when choosing the depth at which the measurement should be made. In a few cases, the formation of air bubbles was observed, which disrupted or even led to the termination of the experiment. However, this can be avoided by carefully setting up the experiment, which requires little practice.

Fluid-cell Raman Spectroscopy (FCRS) enables in operando observations of reaction and transport phenomena during the aqueous corrosion of silicate glasses at a microscopic level, at elevated temperatures, and in real-time. Without interrupting ongoing processes, FCRS provides information about reaction mechanisms, kinetics, and transport processes.

Operando için Akışkan Hücreli Raman Spektroskopisi: Silikat Cam Korozyonu Sırasında Reaksiyon ve Taşınım Olayları Çalışmaları

Fluid-cell Raman Spectroscopy (FCRS) enables the real-time and space-resolved (operando) study of reaction mechanisms, kinetics, and their mutual ...

Fabricating Optical-quality Glass Surfaces to Study Macrophage Fusion

Visualizing the formation of multinucleated giant cells (MGCs) from living specimens has been challenging due to the fact that most live imaging techniques require propagation of light through glass, but on glass macrophage fusion is a rare event. This protocol presents the fabrication of several optical-quality glass surfaces where adsorption of compounds containing long-chain hydrocarbons transforms glass into a fusogenic surface. First, preparation of clean glass surfaces as starting material for surface modification is described. Second, a method is provided for the adsorption of compounds containing long-chain hydrocarbons to convert non-fusogenic glass into a fusogenic substrate. Third, this protocol describes fabrication of surface micropatterns that promote a high degree of spatiotemporal control over MGC formation. Finally, fabricating glass bottom dishes is described. Examples of use of this in vitro cell system as a model to study macrophage fusion and MGC formation are shown.

This protocol describes the fabrication of optical-quality glass surfaces adsorbed with compounds containing long-chain hydrocarbons that can be used to monitor macrophage fusion of living specimens and enables super-resolution microscopy of fixed specimens.

Makrofaj Fusion çalışmaya imalatı kaliteli optik cam yüzeyler

Visualizing the formation of multinucleated giant cells (MGCs) from living specimens has been challenging due to the fact that most live imaging ...

İmmünoloji ve Enfeksiyon

Synthesis of Nine-atom Deltahedral Zintl Ions of Germanium and their Functionalization with Organic Groups

Although the first studies of Zintl ions date between the late 1890's and early 1930's they were not structurally characterized until many years later.1,2 Their redox chemistry is even younger, just about ten years old, but despite this short history these deltahedral clusters ions E9n- (E = Si, Ge, Sn, Pb; n = 2, 3, 4) have already shown interesting and diverse reactivity and have been at the forefront of rapidly developing and exciting new chemistry.3-6 Notable milestones are the oxidative coupling of Ge94- clusters to oligomers and infinite chains,7-19 their metallation,14-16,20-25 capping by transition-metal organometallic fragments,26-34 insertion of a transition-metal atom at the center of the cluster which is sometimes combined with capping and oligomerization,35-47 addition of main-group organometallic fragments as exo-bonded substituents,48-50 and functionalization with various organic residues by reactions with organic halides and alkynes.51-58 
This latter development of attaching organic fragments directly to the clusters has opened up a new field, namely organo-Zintl chemistry, that is potentially fertile for further synthetic explorations, and it is the step-by-step procedure for the synthesis of germanium-divinyl clusters described herein. The initial steps outline the synthesis of an intermetallic precursor of K4Ge9 from which the Ge94- clusters are extracted later in solution. This involves fused-silica glass blowing, arc-welding of niobium containers, and handling of highly air-sensitive materials in a glove box. The air-sensitive K4Ge9 is then dissolved in ethylenediamine in the box and then alkenylated by a reaction with Me3SiC&equiv;CSiMe3. The reaction is followed by electrospray mass spectrometry while the resulting solution is used for obtaining single crystals containing the functionalized clusters [H2C=CH-Ge9-CH=CH2]2-. For this purpose the solution is centrifuged, filtered, and carefully layered with a toluene solution of 18-crown-6. Left undisturbed for a few days, the so-layered solutions produced orange crystalline blocks of [K(18-crown-6)]2[Ge9(HCCH2)2]&bull;en which were characterized by single-crystal X-ray diffraction. 
The process highlights standard reaction techniques, work-up, and analysis towards functionalized deltahedral Zintl clusters. It is hoped that it will help towards further development and understanding of these compounds in the community at large.

We present the high-temperature synthesis of intermetallic precursors K4Ge9, their dissolution in ethylenediamine to form Ge94- deltahedral Zintl ions, and the reaction of the clusters with alkynes to form organo-Zintl ions. The latter are characterized by electrospray mass spectrometry in solutions and by single-crystal X-ray diffraction in the solid state.

Organik Grupları ile Dokuz-atom Deltahedral Zintl Germanyum iyonları ve bunların fonksiyonlandırmalar Sentezi

Although the first studies of Zintl ions date between the late 1890's and early 1930's they were not structurally characterized until many years later.1,2 ...

Sentetik Nükleer Erime Cam Üretimi

Özet

Daha Fazla Video Keşfet

Ex Situ ve yapısal dönüşümleri in Situ soruşturma yöntemleri: Metalik gözlük kristalleşme olgusu

Karmaşık Metal Oksit nano tanecikleri erimiş tuz sentezi

Camdan Metale Sızdırmazlık Yapılarının Optimize Edilmiş Sızdırmazlık Süreci ve Gerçek Zamanlı İzlemesi

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Yeniden Yazılabilir Ekranlar ve Aydınlatma Uygulamaları için Kalıcı Lüminesan Nanopartiküllerin Sentezi

Operando için Akışkan Hücreli Raman Spektroskopisi: Silikat Cam Korozyonu Sırasında Reaksiyon ve Taşınım Olayları Çalışmaları

Makrofaj Fusion çalışmaya imalatı kaliteli optik cam yüzeyler

Organik Grupları ile Dokuz-atom Deltahedral Zintl Germanyum iyonları ve bunların fonksiyonlandırmalar Sentezi