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.

Attenzione: Il processo descritto qui include l&#39;uso di materiale radioattivo (ad esempio, nitrato esaidrato Uranium) e diverse sostanze corrosive. Abbigliamento protettivo ed attrezzature devono essere utilizzati (tra cui un camice da laboratorio, guanti, occhiali di protezione, e una cappa) durante la preparazione del campione. Inoltre, le aree di laboratorio utilizzati per questo lavoro devono essere monitorati regolarmente per contaminazione radioattiva. Nota:. I composti chimici necessari sono elencati nella tabella 1 Questa formulazione è stata sviluppata attraverso l&#39;esame precedentemente riportato dati relativi alla composizione per Trinitite 10 Le frazioni di massa qui riportati sono stati determinati dai media delle frazioni di massa per diversi campioni Trinitite diversi 10 La massa &quot;mancante&quot;.. (frazioni di non somma all&#39;unità) esiste per consentire una maggiore flessibilità quando si aggiunge carburante, manomissione, e altri componenti. La nostra analisi indipendente diversi campioni Trinitite suggerisce che il quarzo è l&#39;unica fase mineralesopravvivere in Trinitite. 5 Perciò, quarzo è l&#39;unico minerale inclusa nel nostro Trinitite formulazione standard (STF). Sebbene i cereali reliquia di altri minerali sono stati segnalati in Trinitite, 11 questi tendono ad essere l&#39;eccezione, non la regola. In generale, il quarzo è l&#39;unico minerale trovato nel vetro fuso. 10,12 Inoltre, sabbia di quarzo è un componente comune di asfalto e calcestruzzo che sarà importante nella formazione del vetro fuso urbano nucleare. <table fo:keep-together.within-page="1"><tbody><tr height="41"><td colspan="2" height="41" style="height:42px;width:317px;"> In media Trinitite dati </td><td colspan="2" style="width:317px;"> Standard Trinitite Formulazione (STF) </td></tr><tr height="22"><td height="22" style="height:22px;width:159px;"> Composto </td><td style="width:159px;"> Frazione di massa </td><td style="width:159px;"> Composto </td><html><td style="width:159px;"> Frazione di massa </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;"> TiO 2 </td><td style="width:159px;"> 4.27x10 -3 </td><td style="width:159px;"> TiO 2 </td><td style="width:159px;"> 4.27x10 -3 </td></tr><tr height="25"><td height="25" style="height:25px;width:159px;"> Totale </td><td style="width:159px;"> 9.81x10 -1 </td><td style="width:159px;"> Totale </td><td style="width:159px;"> 9.91x10 -1 </td></tr></tbody></table> Tabella 1. Elenco dei composti chimici. 1. Preparazione del STF Nota: Attrezzatura necessaria comprende una microbilancia, spatole metalliche, una ceramica mortaio e pestello, cappa, guanti in lattice, un camice da laboratorio e protezione per gli occhi. <ol><li> Miscelazione dei componenti non radioattivi <ol><li> Acquisire almeno 65 g di sabbia di quarzo (SiO 2), 15 g di Al 2 O 3 &lt;/ sub&gt; polvere, 10 g di polvere CaO, 2 g di polvere FeO, 2 g di polvere di MgO, 2 g di Na 2 O in polvere, 7 g di pellet KOH, 1 g di polvere MnO e 1 g di TiO 2 polvere ( composti elencati nella Tabella 1). </li><li> Utilizzare una microbilancia e spatolina di misurare con precisione le frazioni di massa di ciascun composto come elencato nella Tabella 1. Per ottenere i migliori risultati preparare 100 g della matrice precursore non radioattivo in una sola volta. </li><li> Utilizzare un mortaio e pestello per polverizzare (a ~ 10-20 granuli di dimensioni micron) e miscelare accuratamente i composti, formando una miscela di polveri omogenea contenente 64,2 g di SiO 2, 14,2 g di Al 2 O 3, 9,64 g di CaO, 1,97 g di FeO, 1,15 g di MgO, 1,25 g di Na 2 O. 6.12 g di KOH, 0,0505 g di MnO, e 0,427 g di TiO 2. </li><li> Agitare la miscela, utilizzando un mixer palla, poco prima del passaggio successivo è presa. </li></ol></li><li> Miscelazione di STF con uranio nitrato esaidrato (UNH) <ol><li> Acquire di almeno 1 g di UNH. </li><li> All&#39;interno di una cappa aspirante, polverizzare qualche cristallo UNH (utilizzando un mortaio e pestello) per formare una polvere fine di 1-2 micron granuli. </li><li> Aggiungere 33.75 mg di UNH per grammo di matrice precursore non radioattivo (tale rapporto è appropriato per la simulazione di un arma semplice con una resa di 1 kiloton). 13 </li><li> Mescolare bene la miscela di polveri, tra cui l&#39;UNH, utilizzando un mortaio e pestello. Completare mixaggio finale poco prima della fase di fusione. </li></ol></li></ol> 2. La produzione di 1 grammo campione Melt Glass Nota: Attrezzatura necessaria include un HTF valutato a più elevate, di elevata purezza crogioli in grafite, lunghi in acciaio inossidabile pinze crogiolo, guanti resistenti al calore e protezione per gli occhi 1.600 ° C o. Guanti resistenti al calore e protezione per gli occhi devono essere indossati quando si introducono o la rimozione dei campioni dal forno. Occhiali di sicurezza colorato (o occhiali da sole) sono utili in quanto riducono l&#39;abbagliamento dal forno. <ol><li> Produzione di un campione non radioattivo <ol><li> Riempire un piatto di ceramica spessa (come un mortaio) con ~ 100 g di sabbia di quarzo puro e mantenere a RT vicino alla posizione del forno in cui verranno fusi i campioni. </li><li> Preriscaldare il HTF a 1500 ° C. </li><li> Misurare accuratamente 1,00 g della miscela di polveri non radioattivo e posizionare la polvere in un crogiolo di grafite di elevata purezza. </li><li> Posizionare con cura il crogiolo nel HTF riscaldato (con un lungo paio di pinze in acciaio crogiolo) e sciogliere il composto per 30 minuti. </li><li> Rimuovere il campione (di nuovo con le pinze) e versare il campione fuso nel mortaio riempito di sabbia. </li><li> Lasciare che la biglia di vetro che raffreddare per 1-2 minuti prima dell&#39;uso. </li><li> Lucidare il tallone per rimuovere la sabbia residua (se necessario). </li></ol></li><li> Produzione di un campione radioattivo <ol><li> Ripetere i passaggi punti 2.1.1 e 2.1.2 di cui sopra. </li><li> Misurare attentamente 1,00 grammo di miscela di polveri radioattive (comprese UNH) e posizionare il powd<html> er in una elevata purezza crogiolo di grafite con una spatola e microbilancia separato per evitare la contaminazione incrociata. </li><li> Ripetere i punti 2.1.4 - 2.1.6 sopra. </li><li> Monitorare l&#39;area intorno al forno (con un rilevatore portatile di radiazioni e / o saggi magnetiche) per verificare la presenza di contaminazione radioattiva. </li></ol></li></ol> Attivazione 3. Il campione Nota: Le equazioni che seguono sono stati ottenuti ipotizzando l&#39;uso di armi di grado (arricchito) uranio metallico. I quantitativi di UNH o ossido di uranio dovranno essere scalati secondo la frazione di massa di uranio elementare e il livello di 235 U arricchimento. <ol><li> L&#39;attivazione di un campione Melt vetro con uranio Fue <ol><li> Calcolare la frazione di massa di uranio metallico richiesto per il campione utilizzando l&#39;equazione sotto 13 (dove m U rappresenta la frazione di massa di uranio e Y rappresenta la resa arma): 473 / 53473eq1.jpg &quot;/&gt; </li><li> Opzionale: Calcolare la frazione di massa di manomissione (ad esempio, l&#39;uranio naturale, piombo, tungsteno) utilizzando la seguente equazione: 13 <img alt="Equazione 2" src="/files/ftp_upload/53473/53473eq2.jpg" /></li><li> Calcolare il numero di destinazione di fissioni nel campione mediante la seguente equazione 13 dove M s rappresenta la massa del campione in grammi e N f rappresenta il numero di fissioni prodotte nel campione durante l&#39;irraggiamento: <img alt="Equazione 3" src="/files/ftp_upload/53473/53473eq3.jpg" /></li><li> Calcolare il tempo di irraggiamento richiesto utilizzando l&#39;equazione che segue 13 dove m 235 rappresenta la frazione di massa 235 U (livello di arricchimento) e t irr è il tempo di irradiazione in secondi: <img alt="Equazione 4" src="/files/ftp_upload/53473/53473eq4.jpg" /></li><li> Irradiare il campione perT secondi IRR un flusso di neutroni termici di 4,0 x 10 14 n / cm 2 / sec. Ad esempio, un irraggiamento 60 sec in pneumatico tubo 1 (PT-1) a HFIR (con una termica alla risonanza rapporto 35) produrrà circa 1,1 x 10 11 fissioni in un campione contenente 870 mg di UNH (equivalenti a 410 mg di uranio naturale, o 3.0 mg di 235 U). Questo è stato realizzato per una 0,433 g perle di vetro progettato per simulare un campione di vetro fuso prodotta da un&#39;arma con una resa di 0,1 kiloton. Questo campione è stato analizzato a fondo da Cook et al. 14 </li><li> Seguire i protocolli di sicurezza applicabili per la gestione del campione radioattivo post-irradiazione. </li></ol></li><li> L&#39;attivazione di un campione Melt vetro con plutonio carburante (Fattori di pianificazione) <ol><li> Calcolare la frazione di massa di plutonio metallo necessaria per il campione utilizzando l&#39;equazione sotto 13 dove m rappre Puts la frazione di massa di plutonio e Y rappresenta la resa arma: <img alt="Equazione 5" src="/files/ftp_upload/53473/53473eq5.jpg" /></li><li> Ripetere i punti 3.1.2 e 3.1.3 di cui sopra. </li><li> Determinare il tempo di irradiazione necessaria per ottenere il numero desiderato di fissioni nel campione di vetro fuso. Questo tempo dipende dalla composizione e il grado del plutonio così come lo spettro di energia dei neutroni. </li></ol></li></ol> Nota: Grande cura dovrebbe essere presa quando si tratta di plutonio e di ulteriori analisi sarà richiesto. Mentre scrivo, solo l&#39;uranio è stato utilizzato nei campioni di vetro di fusione sintetici prodotti a UT e irradiate a HFIR.

<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).

Nota relativa passi 1.2.2 e 1.2.3: L&#39;importo esatto di UNH varia a seconda dello scenario in simulazione. Le formule di pianificazione sviluppati da Giminaro et al. Possono essere utilizzati per selezionare la massa appropriata di uranio per un dato campione 13 come discusso nella sezione &quot;Attivazione Esempio&quot; di questo documento. Inoltre, ossido di uranio (UO 2 o U 3 O 8) può essere usato al posto di UNH, se disponibile, e la frazione di massa di ...

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.

I campioni non radioattivi prodotti in questo studio sono stati confrontati Trinitite e figure 1-3 mostrano che le proprietà fisiche e la morfologia sono effettivamente simili. La Figura 1 fornisce le fotografie che rivelano le somiglianze di colore e struttura che si osservano a livello macroscopico. La figura 2 mostra microscopio elettronico a scansione (SEM) secondari Electron (SE) le immagini che rivelano caratteristiche simili a livello di micron....

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.

Produzione di sintetico Nucleare Melt Glass

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 Views.  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.

Metodi di Ex Situ ed In Situ indagini sulle trasformazioni strutturali: il caso di cristallizzazione dei vetri metallici

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

Ricerca

Ingegneria

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.

Sali fusi sintesi di nanoparticelle di ossido di metallo complesso

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

Chimica

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.

Processo di sigillamento ottimizzato e monitoraggio in tempo reale delle strutture sigillanti vetro-metallo

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.

Confronto di due diversi metodi di sintesi di singoli cristalli di ditellururo di uranio superconduttore

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

Sintesi idrotermale di nanoparticelle luminescenti persistenti

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.

Autore in primo piano: Avanzamento del bioimaging e della terapia con nanomateriali funzionali

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.

Sintesi di nanoparticelle luminescenti persistenti per display riscrivibili e applicazioni di illuminazione

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.

Spettroscopia Raman a celle fluide per studi operando di fenomeni di reazione e trasporto durante la corrosione del vetro silicato

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.

Realizzazione di superfici di vetro di qualità ottica per studiare macrofago Fusion

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

Immunologia e infezioni

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.

Sintesi di Nine-atomo ioni Deltahedral Zintl del germanio e la loro funzionalizzazione con gruppi organici

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 ...

Produzione di sintetico Nucleare Melt Glass

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Metodi di Ex Situ ed In Situ indagini sulle trasformazioni strutturali: il caso di cristallizzazione dei vetri metallici

Sali fusi sintesi di nanoparticelle di ossido di metallo complesso

Processo di sigillamento ottimizzato e monitoraggio in tempo reale delle strutture sigillanti vetro-metallo

Confronto di due diversi metodi di sintesi di singoli cristalli di ditellururo di uranio superconduttore

Sintesi di nanoparticelle luminescenti persistenti per display riscrivibili e applicazioni di illuminazione

Sintesi di nanoparticelle luminescenti persistenti per display riscrivibili e applicazioni di illuminazione

Sintesi di nanoparticelle luminescenti persistenti per display riscrivibili e applicazioni di illuminazione

Spettroscopia Raman a celle fluide per studi operando di fenomeni di reazione e trasporto durante la corrosione del vetro silicato

Realizzazione di superfici di vetro di qualità ottica per studiare macrofago Fusion

Sintesi di Nine-atomo ioni Deltahedral Zintl del germanio e la loro funzionalizzazione con gruppi organici