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1

Bertrand Fillon, Commissariat à l'Energie Atomique et aux Energies...  

NLE Websites -- All DOE Office Websites (Extended Search)

l'Energie Atomique et aux Energies Alternatives, Challenges for the Future Sustainable Energy Generation, Distribution and Use Bertrand Fillon, Commissariat ...

2

Agreement between the U.S. Department of Energy and the Commissariat a  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

U.S. Department of Energy and the U.S. Department of Energy and the Commissariat a L'Energie Atomique of France for Cooperation in Advanced Nuclear Reactor Science and Technology Agreement between the U.S. Department of Energy and the Commissariat a L'Energie Atomique of France for Cooperation in Advanced Nuclear Reactor Science and Technology The purpose of this Implementing Arrangement is to establish between the Department of Energy of the United States of America and the Commissariat a l'Energie Atomique of France, hereinafter referred to as the parties, terms for bilateral collaboration on Research and Development focused on advanced technologies for improving the costs, safety, and proliferation-resistance of nuclear power systems. 4.5.1.1.3.4_france_agreement.pdf More Documents & Publications

3

CX-005780: Categorical Exclusion Determination | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

80: Categorical Exclusion Determination 80: Categorical Exclusion Determination CX-005780: Categorical Exclusion Determination Sintered Copper Zinc Tin Selenium Nanoparticle Solar Cells on Metal Foil CX(s) Applied: A9, A11, B3.6 Date: 05/11/2011 Location(s): San Jose, California Office(s): Energy Efficiency and Renewable Energy, Golden Field Office The Photovoltaic (PV) Technology Incubator project represents a significant component of the United States (U.S.) Department of Energy (DOE) business strategy of partnering with U.S. industry to accelerate the commercialization of photovoltaic system research and development (R&D) to meet aggressive cost and installed capacity goals. DOCUMENT(S) AVAILABLE FOR DOWNLOAD CX-005780.pdf More Documents & Publications Bertrand Fillon, Commissariat à l'Energie Atomique et aux Energies

4

Spectral properties of the Google matrix of the World Wide Web and other directed networks Bertrand Georgeot, Olivier Giraud,* and Dima L. Shepelyansky  

E-Print Network (OSTI)

Spectral properties of the Google matrix of the World Wide Web and other directed networks Bertrand of the Google matrix of various examples of directed networks such as vocabulary networks of dictionaries eigenvalue for Google damping parameter equal to unity. The vocabulary networks have relatively homogeneous

Shepelyansky, Dima

5

On the uniqueness of Bertrand equilibrium  

Science Conference Proceedings (OSTI)

We introduce product differentiation in the model of price competition with strictly convex costs in which firms have to supply all of the forthcoming demand. We find that although a continuum of equilibria exists in a homogeneous product market, the ... Keywords: Increasing marginal cost, Price competition, Product differentiation, Strictly convex cost, Uniqueness of equilibrium

Daisuke Hirata; Toshihiro Matsumura

2010-11-01T23:59:59.000Z

6

Principles of Package Design Bertrand Meyer  

E-Print Network (OSTI)

List(lastpage) Fig. 4. Structure of the Manuals. USER / \\ APPLICATION / PROGRAM / ~ PACKAGE ~ , ~ SYSTEM / (compiler Issues The programming language for writing a package should offer a structure corresponding a program structure ("class" in Simula and "package" in Ada) with three cate- gories of elements: data

Meyer, Bertrand

7

Prices, capacities and service quality in a congestible Bertrand duopoly  

E-Print Network (OSTI)

Dender, Kurt. 2004. “Duopoly prices under congested access,”of demand on capacities and prices, see (3), has been madefacilities, even when price discrimination is allowed. r dq

De Borger, Bruno; Van Dender, Kurt

2005-01-01T23:59:59.000Z

8

Processors and their collection Bertrand Meyer1,2,3  

E-Print Network (OSTI)

for calls. The SCOOP type system [8] guarantees semantic consistency; in particular it is not permitted have terminated and the object OA that contained it may have been reclaimed. It is still obligated (constructor). #12;5 reclaimed, they will waste resources, and possibly lead to resource exhaustion and program

Meyer, Bertrand

9

UNIVERSITE DE BOURGOGNE COMMISSARIAT A L'ENERGIE ATOMIQUE de Saclay  

E-Print Network (OSTI)

........................................................ 23 B. Similitudes entre les SOFC et les cellules EHT pour les interconnecteurs des piles à combustibles de type SOFC (Solid Oxide Fuel Cell). Cette pièce'anode. B. Similitudes entre les SOFC et les cellules EHT Il est important de signaler comme le montre la

10

Synthesis of Donor Ligands and Their Applications in Catalysis  

E-Print Network (OSTI)

Bertrand, G. Angewandte Chemie International Edition 2005,Bertrand, G. Angewandte Chemie International Edition 2005,Bertrand, G. Angewandte Chemie International Edition 2008,

DeHope, Alan

2010-01-01T23:59:59.000Z

11

IRIM at TRECVID 2011: Semantic Indexing and Instance Search Bertrand Delezoide1  

E-Print Network (OSTI)

computation. LIG/stip : bag of word, STIP lo- cal descriptor, generated using Ivan Laptev's soft 1000 1000 0.300 200 0.0939 LIG/opp sift dense unc 1000 1000 0.450 250 0.1071 LIG/stip hof 256 256 0.450 128 0.0360 LIG/stip hog 256 256 0.500 128 0.0550 LIG/stip hof 1000 1000 0.400 175 0.0408 LIG/stip hog

Paris-Sud XI, Université de

12

Higher Prices from Entry: Pricing of Brand-Name Drugs  

E-Print Network (OSTI)

4 Bertrand and Cartel Prices Vary with z 7T, CS L Figure 5Distance Cumulative Abnormal Price Changes (%) Dissimilarof New Drug Figure 6 Cumulative Unexpected Price Effects

Perloff, Jeffrey M.; Suslow, Valerie Y.; Seguin, Paul J.

1995-01-01T23:59:59.000Z

13

Consequences of low dose irradiation in the CNS  

NLE Websites -- All DOE Office Websites (Extended Search)

Consequences of low dose irradiation in the CNS Bertrand Tseng, Munjal M. Acharya, Neal Patel, Katherine Tran, Mary Lan, Erich Giedzinski, Vipan Kumar and Charles Limoli Department...

14

Linking Science and Technology for Global Solutions  

Science Conference Proceedings (OSTI)

Dec 15, 2007 ... regeneration chemistry for inhibiting erosion and enhancing ...... 2Commissariat à l'Énergie Atomique/SRMA; 3Laboratoire Systémes et.

15

Symbolic Test Selection Based on Approximate Analysis  

E-Print Network (OSTI)

Symbolic Test Selection Based on Approximate Analysis Bertrand Jeannet, Thierry J´eron, Vlad Rusu}@irisa.fr Abstract. This paper addresses the problem of generating symbolic test cases for testing the conformance. The challenge we consider is the selection of test cases according to a test purpose, which is here a set

Paris-Sud XI, Université de

16

Robust algorithm for tunnel closing in 3D volumetric objects based on topological characteristics of points  

Science Conference Proceedings (OSTI)

In this letter, we propose a robust, linear in time modification of Aktouf, Bertrand and Perroton's algorithm for tunnel (3D hole) closing in 3D volumetric objects. Our algorithm is insensitive to small distortions and branches. The algorithm has been ... Keywords: 3D image processing, Crack bridging, Skeletonisation, Topological numbers, Tunnel closing

Marcin Janaszewski; Micha? Postolski; Laurent Babout

2011-12-01T23:59:59.000Z

17

BioMed Central Page 1 of 10  

E-Print Network (OSTI)

counterpart. Nature 1994, 367:453-455. 25. Grenier S, Pintureau B, Heddi A, Lassabliere F, Jager C, Louis C Biol 1994, 4(6):537-540. 45. Sinkins SP, Curtis CF, O'Neill SL: The potential application of inherited bipunctata). Journal of Bacteriology 1994, 176:388-394. 49. Hurst GDD, Jiggins FM, Schulenberg JHG, Bertrand

Tinsley, Matt

18

The National Marine Fisheries Service Habitat Conservation Efforts in Louisiana, 1980 Through 1990  

E-Print Network (OSTI)

% of all remaining coastal wetlands in the United States. Louisiana waters contributed about 15 tively estimated to exceed $600 mil lion (Bertrand, 1984). Louisiana coastal wetlands converted to open). Wetland losses in Louisiana are caused by a variety of factors. In a com prehensive evaluation, Turner

19

hal00281082, VARIATIONAL CHARACTERIZATIONS OF THE EFFECTIVE MULTIPLICATION  

E-Print Network (OSTI)

in nuclear reactor theory. This work follows a very recent paper by M. Mokhtar­ Kharroubi [22] devoted FACTOR OF A NUCLEAR REACTOR CORE Bertrand LODS Université Blaise Pascal (Clermont II) Laboratoire de. KEYWORDS: effective multiplication factor, nuclear reactor, neutron transport equation, energy

Paris-Sud XI, Université de

20

hal-00281082,version1-20May2008 VARIATIONAL CHARACTERIZATIONS OF THE EFFECTIVE MULTIPLICATION  

E-Print Network (OSTI)

multiplication factor arising in nuclear reactor theory. This work follows a very recent paper by M. Mokhtar FACTOR OF A NUCLEAR REACTOR CORE Bertrand LODS Universit´e Blaise Pascal (Clermont II) Laboratoire de­dependent diffusion equation. KEYWORDS: effective multiplication factor, nuclear reactor, neutron transport equation

Paris-Sud XI, Université de

Note: This page contains sample records for the topic "bertrand fillon commissariat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

LYSINE, METHIONINE AND CYSTINE REQUIREMENTS OF SEMI-HEAVY LAYERS  

E-Print Network (OSTI)

LYSINE, METHIONINE AND CYSTINE REQUIREMENTS OF SEMI-HEAVY LAYERS M. PICARD S. BERTRAND J. SALVERT Service zootechnique, A. E. C., 03600 Commentry Two different strains of commercial semi-heavy layers of lysine. This trial confirms our previous works. A semi-heavy layer is largely satisfied by a feed

Recanati, Catherine

22

Agreement between the Department of Energy of the United States of America  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Department of Energy of the United States of Department of Energy of the United States of America and the Commissariat a l'Energie Atomique of France Agreement between the Department of Energy of the United States of America and the Commissariat a l'Energie Atomique of France To amend Article 12.1 of the Agreement to read as follows: "This Agreement shall enter into force upon the latter date of signature, shall remain in force for five (5) years, and subject to Article 12.3 shall be automatically renewed for additional five-year periods." This Amendment shall enter into force upon signature by both Parties, with effect from September 18, 2005. 4.5.1.1.3.4_france_amendment.pdf More Documents & Publications Agreement between the U.S. Department of Energy and the Commissariat a L'Energie Atomique of France for Cooperation in Advanced Nuclear Reactor

23

New Experimental Studies of Thermal-Hydraulics of Rod Bundles (NESTOR)  

Science Conference Proceedings (OSTI)

The NESTOR (New Experimental Studies of Thermal-hydraulics of Rod Bundles) project is a multi-year collaborative endeavor of EPRI, Electricit de France (EDF), and Commissariat lEnergie Atomique (CEA). The project is aimed at elucidating thermal-hydraulics unknowns pertaining to axial offset anomaly (AOA) in pressurized water reactor (PWR) cores.

2008-12-22T23:59:59.000Z

24

New Experimental Studies of Thermal Hydraulics of Rod Bundles (NESTOR)  

Science Conference Proceedings (OSTI)

The NESTOR project (that is, new experimental studies of thermal hydraulics of rod bundles) is a multiyear collaborative endeavor of the Electric Power Research Institute (EPRI), Electricit de France (EDF), and Commissariat a lEnergie Atomique (CEA). The project is aimed at elucidating thermal-hydraulics unknowns pertaining to axial offset anomaly (AOA) in pressurized water reactor (PWR) cores.

2011-10-26T23:59:59.000Z

25

New Experimental Studies of Thermal-Hydraulics in Rod Bundles (NESTOR)  

Science Conference Proceedings (OSTI)

The NESTOR (New Experimental Studies of Thermal-Hydraulics of Rod Bundles) project is a multiyear collaborative endeavor of EPRI, Electricitde France (EDF), and Commissariat l'Energie Atomique (CEA). The project is aimed at elucidating thermal-hydraulics unknowns pertaining to axial offset anomaly (AOA) in pressurized water reactor (PWR) cores.

2006-12-19T23:59:59.000Z

26

emissions2Global and regional drivers of accelerating CO Gernot Klepper, and Christopher B. Field  

E-Print Network (OSTI)

Material www.pnas.org/cgi/content/full/0700609104/DC1 Supplementary material can be found at: www, TN 37831; §Commissariat a` l'Energie Atomique, Laboratorie des Sciences du Climat et de l of earlier declining trends in the energy intensity of gross domestic product (GDP) (energy

27

Elementary excitations of liquid 4 He in aerogel  

E-Print Network (OSTI)

Elementary excitations of liquid 4 He in aerogel O. Plantevin and B. Fa°k Commissariat a` l-roton excitations of liquid 4 He immersed in aerogel of 95% porosity have been measured using inelastic neutron.25 K. Aerogel grown with deuterated materials not exposed to air was used and measure- ments in bulk

Glyde, Henry R.

28

New Experimental Studies of Thermal-Hydraulics of Rod Bundles (NESTOR)  

Science Conference Proceedings (OSTI)

NESTOR (New Experimental Studies of Thermal-hydraulics of Rod Bundles) project is a multiyear collaborative endeavor of EPRI, Electricite de France (EDF), and Commissariat a l'Energie Atomique (CEA). The project is aimed at elucidating thermal-hydraulics unknowns pertaining to the problem of axial offset anomaly (AOA) in PWR cores.

2005-12-05T23:59:59.000Z

29

Joint EPRI-CEA Research on Small Punch Testing for Nuclear Application  

Science Conference Proceedings (OSTI)

A joint research project between EPRI and the Commissariat a l'Energie Atomique (CEA) has been under way since 1998 to compare the fracture behavior of reactor pressure vessel (RPV) materials in the transition region as tested by a subsize impact test (Charpy) and subsize specimen techniques. This report summarizes the progress made under this joint effort.

2001-12-13T23:59:59.000Z

30

* Indique que le rcipiendaire est dcd. Page 1 sur 4 RCIPIENDAIRES DE LA MDAILLE  

E-Print Network (OSTI)

. Léonce Montambault, sciences et génie 1989 Le Dr Roger R. Dozois, médecine M. Raymond Sirois, sciences de Bertrand Blanchet, théologie et sciences religieuses L'Honorable Paule Gauthier, droit M. Claude R. Jacques Lamarre, sciences et génie M. Paul Lévesque, sciences et génie M. Michel R. Saint-Pierre, sciences

Pouliot, Jacynthe

31

New Experimental Studies of Thermal-Hydraulics of Rod Bundles (NESTOR): Final Synthesis  

Science Conference Proceedings (OSTI)

The New Experimental Studies of Thermal-Hydraulics of Rod Bundles (NESTOR) project was a multi-year collaborative endeavor of the Electric Power Research Institute (EPRI), Electricité de France (EDF), and Commissariat à l´Energie Atomique et aux Energies Alternatives (CEA). The project aimed at elucidating Thermal-Hydraulics (T/H) unknowns pertaining to Crud Induced Power Shift (CIPS) - formerly called axial offset anomaly (AOA) - in Pressurized Water Reactor (PWR) ...

2013-06-28T23:59:59.000Z

32

Amendment to the Agreement between the Department of Energy of the United States of America and the Commisariat a LEnergie Atomique of France for Cooperation in Advanced Nuclear Reactor Science and Technology  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

AVENANT AVENANT it I'ACCORD entre LE DEPARTMENT OF ENERGY DES ETATS-UNIS D'AMERIQUE et LE COMMISSARIAT A L'ENERGIE ATOMIQUE FRANCAIS POUR UNE COOPERATION SCIENTIFIQUE ET TECHNIQUE DANS LE DOMAINE DES REACTEURS NUCLEAIRES DE TYPE AVANCE Le Department of Energy des Etats Unis d'Amerique et Ie Commissariat a l'Energie Atomique fran<;ais(ci-apres « les Parties») ; Agissant conformement a I'Article 12.2 de l'Accord entre Ie Department of Energy des Etats Unis d'Amerique et Ie Commissariat a l'Energie Atomique fran<;ais pour une cooperation scientifique et technique dans Ie domaine des reacteurs nucleaires de type avance du 18 septembre 2000 (ci-apres designe« l'Accord ») ; Ont convenu ce qui suit: De modifier l'Article 12.1 de l'Accord de la maniere suivante: « Cet Accord entrera en vigueur a la derniere en date des signatures et demeurera en vigueur pour cinq (5) ans, et sous

33

Assessment  

NLE Websites -- All DOE Office Websites (Extended Search)

Genetic Genetic Variability of Cell Wall Degradability for the Selection of Alfalfa with Improved Saccharification Efficiency Marc-Olivier Duceppe & Annick Bertrand & Sivakumar Pattathil & Jeffrey Miller & Yves Castonguay & Michael G. Hahn & Réal Michaud & Marie-Pier Dubé # Her Majesty the Queen in Right of Canada 2012 Abstract Alfalfa (Medicago sativa L.) has a high potential for sustainable bioethanol production, particularly because of its low reliance on N fertilizer. We assessed near-infrared reflec- tance spectroscopy (NIRS) as a high-throughput technique to measure cell wall (CW) degradability in a large number of lignified alfalfa stem samples. We also used a powerful immu- nological approach, glycome profiling, and chemical analyses to increase our knowledge of the composition of CW poly- saccharides of alfalfa stems with various levels

34

Consequences of low dose irradiation in the CNS  

NLE Websites -- All DOE Office Websites (Extended Search)

Consequences of low dose irradiation in the CNS Consequences of low dose irradiation in the CNS Bertrand Tseng University of California Abstract Radiation-induced oxidative stress can impact the physiologic function of multipotent neural stem and precursor cells by activating redox-sensitive signaling cascades that can alter radiosensitivity, mitochondrial function, and cell fate. Many of these signaling pathways depend on the nature, magnitude and duration of the specific reactive species involved, features that dictate in large part whether radiation-induced changes are harmful or beneficial to the organism. We have shown that acute low dose irradiation (2-20 cGy) can elicit significant increases in reactive oxygen (ROS) and nitrogen (RNS) species over several days to weeks. These redox changes can

35

Peirce's Truth-functiona Analysis and the Origin of Truth Tables  

E-Print Network (OSTI)

We explore the technical details and historical evolution of Charles Peirce's articulation of a truth table in 1893, against the background of his investigation into the truth-functional analysis of propositions involving implication. In 1997, John Shosky discovered, on the verso of a page of the typed transcript of Bertrand Russell's 1912 lecture on "The Philosophy of Logical Atomism" truth table matrices. The matrix for negation is Russell's, alongside of which is the matrix for material implication in the hand of Ludwig Wittgenstein. It is shown that an unpublished manuscript identified as composed by Peirce in 1893 includes a truth table matrix that is equivalent to the matrix for material implication discovered by John Shosky. An unpublished manuscript by Peirce identified as having been composed in 1883-84 in connection with the composition of Peirce's "On the Algebra of Logic: A Contribution to the Philosophy of Notation" that appeared in the American Journal of Mathematics in 1885 includes an example ...

Anellis, Irving H

2011-01-01T23:59:59.000Z

36

Small Modular Fast Reactor Design Description Joint Effort  

NLE Websites -- All DOE Office Websites (Extended Search)

July 1, 2005 ANL-SMFR-1 July 1, 2005 ANL-SMFR-1 Small Modular Fast Reactor Design Description Joint Effort by Argonne National Laboratory (ANL) Commissariat a l'Energie Atomique (CEA) and Japan Nuclear Cycle Development Institute (JNC) Project Leaders Y. I. Chang and C. Grandy, ANL P. Lo Pinto, CEA M. Konomura, JNC Technical Contributors ANL: J. Cahalan, F. Dunn, M. Farmer, S. Kamal, L. Krajtl, A. Moisseytsev, Y. Momozaki, J. Sienicki, Y. Park, Y. Tang, C. Reed, C. Tzanos, S. Wiedmeyer, and W. Yang CEA: P. Allegre, J. Astegiano, F. Baque, L. Cachon, M. S. Chenaud, J-L Courouau, Ph. Dufour, J. C. Klein, C. Latge, C. Thevenot, and F. Varaine JNC: M. Ando, Y. Chikazawa, M. Nagamura, Y. Okano, Y. Sakamoto,

37

Electron Ion Collider: The Next QCD Frontier Understanding  

NLE Websites -- All DOE Office Websites (Extended Search)

Electron Electron Ion Collider: The Next QCD Frontier Understanding the glue that binds us all White Paper Writing Committee Elke C. Aschenauer Brookhaven National Laboratory William Brooks Universidad T´ ecnica Federico Santa Maria Abhay Deshpande 1 Stony Brook University Markus Diehl Deutsches Elektronen-Synchrotron DESY Haiyan Gao Duke University Roy Holt Argonne National Laboratory Tanja Horn The Catholic University of America Andrew Hutton Thomas Jefferson National Accelerator Facility Yuri Kovchegov The Ohio State University Krishna Kumar University of Massachusetts, Amherst Zein-Eddine Meziani 1 Temple University Alfred Mueller Columbia University Jianwei Qiu 1 Brookhaven National Laboratory Michael Ramsey-Musolf University of Wisconsin Thomas Roser Brookhaven National Laboratory 1 Co-Editor 1 Franck Sabati´ e Commissariat ` a l' ´ Energie Atomique-Saclay

38

Experimental power density distribution benchmark in the TRIGA Mark II reactor  

Science Conference Proceedings (OSTI)

In order to improve the power calibration process and to benchmark the existing computational model of the TRIGA Mark II reactor at the Josef Stefan Inst. (JSI), a bilateral project was started as part of the agreement between the French Commissariat a l'energie atomique et aux energies alternatives (CEA) and the Ministry of higher education, science and technology of Slovenia. One of the objectives of the project was to analyze and improve the power calibration process of the JSI TRIGA reactor (procedural improvement and uncertainty reduction) by using absolutely calibrated CEA fission chambers (FCs). This is one of the few available power density distribution benchmarks for testing not only the fission rate distribution but also the absolute values of the fission rates. Our preliminary calculations indicate that the total experimental uncertainty of the measured reaction rate is sufficiently low that the experiments could be considered as benchmark experiments. (authors)

Snoj, L.; Stancar, Z.; Radulovic, V.; Podvratnik, M.; Zerovnik, G.; Trkov, A. [Josef Stefan Inst., Jamova cesta 39, SI-1000 Ljubljana (Slovenia); Barbot, L.; Domergue, C.; Destouches, C. [CEA DEN, DER, Instrumentation Sensors and Dosimetry laboratory Cadarache, F-13108 Saint-Paul-Lez-Durance (France)

2012-07-01T23:59:59.000Z

39

CONVERSION OF RUSSIAN WEAPON-GRADE PLUTONIUM INTO OXIDE FOR MIXED OXIDE (MOX) FUEL FABRICATION.  

SciTech Connect

Progress has been made in the Russian Federation towards the conversion of weapons-grade plutonium (w-Pu) into plutonium oxide (PuO{sub 2}) suitable for further manufacture into mixed oxide (MOX) fuels. This program is funded both by French Commissariat x 1'Energie Atomique (CEA) and the US National Nuclear Security Administration (NNSA). The French program was started as a way to make available their expertise gained from manufacturing MOX fuel. The US program was started in 1998 in response to US proliferation concerns and the acknowledged international need to decrease available w-Pu. Russia has selected both the conversion process and the manufacturing site. This paper discusses the present state of development towards fulfilling this mission: the demonstration plant designed to process small amounts of Pu and validate all process stages and the industrial plant that will process up to 5 metric tons of Pu per year.

Glagovski, E.; Kolotilov, Y.; Glagolenko, Y.; Zygmunt, Stanley J.; Mason, C. F. V. (Caroline F. V.); Hahn, W. K. (Wendy K.); Durrer, R. E. (Russell E.); Thomas, S.; Sicard, B.; Herlet, N.; Fraize, G.; Villa, A.

2001-01-01T23:59:59.000Z

40

Document Library | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Services » Document Library Services » Document Library Document Library January 30, 2006 International Nuclear Energy Research Initiative: Annual Report 2005 The International Nuclear Energy Research Initiative (I-NERI) supports the National Energy Policy by conducting research to advance the state of nuclear science and technology in the United States. I-NERI sponsors innovative scientific and engineering research and development (R&D) in cooperation with participating countries. The research performed under the I-NERI umbrella addresses the key issues affecting the future of nuclear energy and its global deployment. September 18, 2005 Agreement between the Department of Energy of the United States of America and the Commissariat a l'Energie Atomique of France To amend Article 12.1 of the Agreement to read as follows:

Note: This page contains sample records for the topic "bertrand fillon commissariat" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Oxygen reduction in PEM fuel cell conditions: Heat-treated macrocycles and beyond  

NLE Websites -- All DOE Office Websites (Extended Search)

reduction in PEM fuel cell conditions: reduction in PEM fuel cell conditions: Heat-treated macrocycles and beyond J. P. Dodelet INRS-Énergie et Matériaux C. P. 1020, Varennes, Québec, Canada, J3X 1S2 dodelet@inrs-ener.uquebec.ca Collaborators Michel Lefèvre (INRS) Sébastien Marcotte (INRS) Frédéric Jaouen (Royal Inst. of Technology, Sweden) Prof. Patrick Bertrand (Université Catholique de Louvain, Belgium) Prof. Göran Lindbergh (Royal Inst. Of Technology, Sweden) New Orleans workshop March 21 03. DODELET, J. P. ; New Orleans, March 21, 03 1 PEM Fuel Cells Anode : 2 H 2 → 4 H + + 4 e - Electrolyte : Perfluorinated polymer - SO 3 H Cathode : O 2 + 4 H + + 4 e - → 2 H 2 O Acidic Medium ( pH ~ 1 ) Low Temperature Fuel Cell (80°C) ↓ Pt- based Anode and Cathode Catalysts Pt is not abundant and expensive

42

European gas market study sees limited role for LNG imports  

Science Conference Proceedings (OSTI)

An analysis of the Western European gas market published by the European Investment Bank concludes that although the share of imports will grow, existing suppliers Algeria, Russia, and Norway can meet projected demand until and perhaps even beyond 2010. {open_quotes}Alternative sources are not necessary, although Europe might call upon long-distance suppliers to diversify supply sources,{close_quotes} says study author Bertrand Rossert. The gas demand in Western Europe is estimated to grow from 335 bcm in 1995 to 390 bcm by 2000 and 410-450 bcm in 2010, led by the power and residential sectors. Demand in the electricity sector in Belgium, France, Germany, Italy, the Netherlands, Portugal, Spain, and the U.K. should grow rapidly from 40 bcm in 1995 to 70 bcm in 2000 and at a slower rate thereafter. Beyond 2005, the expansion of gas-fired generation will depend on nuclear power policies. (In Eastern Europe, projections are more problematic because of political and economic uncertainties, but could grow from 70 bcm in 1995 to 100 bcm in 2005 and around 110 bcm in 2010).

NONE

1996-12-31T23:59:59.000Z

43

Plant maintenance and advanced reactors issue, 2008  

Science Conference Proceedings (OSTI)

The focus of the September-October issue is on plant maintenance and advanced reactors. Major articles/reports in this issue include: Technologies of national importance, by Tsutomu Ohkubo, Japan Atomic Energy Agency, Japan; Modeling and simulation advances brighten future nuclear power, by Hussein Khalil, Argonne National Laboratory, Energy and desalination projects, by Ratan Kumar Sinha, Bhabha Atomic Research Centre, India; A plant with simplified design, by John Higgins, GE Hitachi Nuclear Energy; A forward thinking design, by Ray Ganthner, AREVA; A passively safe design, by Ed Cummins, Westinghouse Electric Company; A market-ready design, by Ken Petrunik, Atomic Energy of Canada Limited, Canada; Generation IV Advanced Nuclear Energy Systems, by Jacques Bouchard, French Commissariat a l'Energie Atomique, France, and Ralph Bennett, Idaho National Laboratory; Innovative reactor designs, a report by IAEA, Vienna, Austria; Guidance for new vendors, by John Nakoski, U.S. Nuclear Regulatory Commission; Road map for future energy, by John Cleveland, International Atomic Energy Agency, Vienna, Austria; and, Vermont's largest source of electricity, by Tyler Lamberts, Entergy Nuclear Operations, Inc. The Industry Innovation article is titled Intelligent monitoring technology, by Chris Demars, Exelon Nuclear.

Agnihotri, Newal (ed.)

2009-09-15T23:59:59.000Z

44

Chernobyl bibliography  

Science Conference Proceedings (OSTI)

The purpose of the DOE/OHER Chernobyl Database project is to create and maintain an information system to provide usable information for research studies related to the nuclear accident. The system is the official United States repository for information about the Chernobyl accident and its consequences, and currently includes an extensive bibliography and diverse radiological measurements with supporting information. PNL has established two resources: original (not summarized) measurement data, currently about 80,000 measurements, with ancillary information; and about 2,200 bibliographic citations, some including abstracts. Major organizations that have contributed radiological measurement data include the Washington State Department of Social and Health Services; United States Environmental Protection Agency (domestic and foreign data); United States Nuclear Regulatory Commission; Stone Webster; Brookhaven National Laboratory; Commissariat A L'energie Atomique in France; Ministry of Agriculture, Fisheries, and Food in the United Kingdom; Japan National Institute of Radiological Sciences; and the Finnish Centre For Radiation and Nuclear Safety (STUK). Scientists in Australia, Austria, Belgium, Canada, China, Denmark, England, Federal Republic of Germany, Finland, France, Ireland, Italy, Japan, the Netherlands, Romania, Scotland, Spain, Sweden, Switzerland, United States, Wales, and Yugoslavia have made contributions. Bibliographic materials have been obtained from scientists in the above countries that have replied to requests. In addition, literature searches have been conducted, including a search of the DOE Energy Database. The last search was conducted in January, 1989. This document lists the bibliographic information in the DOE/OHER Chernobyl Database at the current time.

Carr, F. Jr.; Mahaffey, J.A.

1989-09-01T23:59:59.000Z

45

PNNL Results from 2010 CALIBAN Criticality Accident Dosimeter Intercomparison Exercise  

SciTech Connect

This document reports the results of the Hanford personnel nuclear accident dosimeter (PNAD) and fixed nuclear accident dosimeter (FNAD) during a criticality accident dosimeter intercomparison exercise at the CEA Valduc Center on September 20-23, 2010. Pacific Northwest National Laboratory (PNNL) participated in a criticality accident dosimeter intercomparison exercise at the Commissariat a Energie Atomique (CEA) Valduc Center near Dijon, France on September 20-23, 2010. The intercomparison exercise was funded by the U.S. Department of Energy, Nuclear Criticality Safety Program, with Lawrence Livermore National Laboratory as the lead Laboratory. PNNL was one of six invited DOE Laboratory participants. The other participating Laboratories were: Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Savannah River Site (SRS), the Y-12 National Security Complex at Oak Ridge, and Sandia National Laboratory (SNL). The goals of PNNL's participation in the intercomparison exercise were to test and validate the procedures and algorithm currently used for the Hanford personnel nuclear accident dosimeters (PNADs) on the metallic reactor, CALIBAN, to test exposures to PNADs from the side and from behind a phantom, and to test PNADs that were taken from a historical batch of Hanford PNADs that had varying degrees of degradation of the bare indium foil. Similar testing of the PNADs was done on the Valduc SILENE test reactor in 2009 (Hill and Conrady, 2010). The CALIBAN results are reported here.

Hill, Robin L.; Conrady, Matthew M.

2011-10-28T23:59:59.000Z

46

Performance Improvements to the Neutron Imaging System at the National Ignition Facility  

SciTech Connect

A team headed by LANL and including many members from LLNL and NSTec LO and NSTec LAO fielded a neutron imaging system (NIS) at the National Ignition Facility at the start of 2011. The NIS consists of a pinhole array that is located 32.5 cm from the source and that creates an image of the source in a segmented scintillator 28 m from the source. The scintillator is viewed by two gated, optical imaging systems: one that is fiber coupled, and one that is lens coupled. While there are a number of other pieces to the system related to pinhole alignment, collimation, shielding and data acquisition, those pieces are discussed elsewhere and are not relevant here. The system is operational and has successfully obtained data on more that ten imaging shots. This remainder of this whitepaper is divided in five main sections. In Section II, we identify three critical areas of improvement that we believe should be pursued to improve the performance of the system for future experiments: spatial resolution, temporal response and signal-to-noise ratio. In Section III, we discuss technologies that could be used to improve these critical performance areas. In Section IV, we describe a path to evolve the current system to achieve improved performance with minimal impact on the ability of the system to operate on shots. In Section V, we discuss the abilities, scope and timescales of the current teams and the Commissariat energie atomique (CEA). In Section VI, we summarize and make specific recommendations for collaboration on improvements to the NIS.

Fittinghoff, D N; Bower, D E; Drury, O B; Dzenitis, J M; Hatarik, R; Merrill, F E; Grim, G P; Wilde, C H; Wilson, D C; Landoas, O; Caillaud, T; Bourgade, J; Buckles, R A; Lee, J; Weiss, P B

2011-09-26T23:59:59.000Z

47

Lifetime Extension of the Phenix Plant  

SciTech Connect

The French fast reactor prototype Phenix was put into commercial operation in 1974. The total time of power operation of the plant is [approximately]100000 h representing 3860 equivalent fuel power days (EFPD). With the initial objective of the demonstration of fast breeder reactors achieved, since the early 1990s, the role of the reactor as an irradiation facility has been emphasized, particularly in support of the Commissariat a l'Energie Atomique research and development program on long-lived radioactive waste transmutation. This new objective required an extension of the planned reactor lifetime. A major renovation program was carried out in the plant from 1994 to 2003, involving safety upgrading, component inspections and repairs, and the 10-yr statutory maintenance. The main work consisted of the addition of a backup control rod to the reactor; improvement of earthquake protection by reinforcement of buildings and components and replacement of the emergency water cooling circuit; improvement of protection against sodium fire by partitioning the secondary sodium circuit in the steam generator building, reinforcement of steam generator casing, and installation of an antiwhip system on the high-pressure steam pipes; replacement of hot parts of the 321 stainless steel secondary loops and steam generator modules, affected by delayed reheat cracking; special inspections of the reactor internal structures to demonstrate their good condition. An extensive plant requalification program was carried out following the renovation work, and the plant resumed power operation in June 2003. Six operating cycles are planned, representing a total irradiation time of 720 EFPD equivalent to [approximately]5.5 yr of operation.

Guidez, J. [Commissariat a l'Energie Atomique (France); Le Coz, P. [Commissariat a l'Energie Atomique (France); Martin, L. [Commissariat a l'Energie Atomique (France); Mariteau, P. [Electricite de France (France); Dupraz, R. [Framatome-ANP (France)

2005-04-15T23:59:59.000Z

48

The National Ignition Facility and the Path to Fusion Energy  

SciTech Connect

The National Ignition Facility (NIF) is operational and conducting experiments at the Lawrence Livermore National Laboratory (LLNL). The NIF is the world's largest and most energetic laser experimental facility with 192 beams capable of delivering 1.8 megajoules of 500-terawatt ultraviolet laser energy, over 60 times more energy than any previous laser system. The NIF can create temperatures of more than 100 million degrees and pressures more than 100 billion times Earth's atmospheric pressure. These conditions, similar to those at the center of the sun, have never been created in the laboratory and will allow scientists to probe the physics of planetary interiors, supernovae, black holes, and other phenomena. The NIF's laser beams are designed to compress fusion targets to the conditions required for thermonuclear burn, liberating more energy than is required to initiate the fusion reactions. Experiments on the NIF are focusing on demonstrating fusion ignition and burn via inertial confinement fusion (ICF). The ignition program is conducted via the National Ignition Campaign (NIC) - a partnership among LLNL, Los Alamos National Laboratory, Sandia National Laboratories, University of Rochester Laboratory for Laser Energetics, and General Atomics. The NIC program has also established collaborations with the Atomic Weapons Establishment in the United Kingdom, Commissariat a Energie Atomique in France, Massachusetts Institute of Technology, Lawrence Berkeley National Laboratory, and many others. Ignition experiments have begun that form the basis of the overall NIF strategy for achieving ignition. Accomplishing this goal will demonstrate the feasibility of fusion as a source of limitless, clean energy for the future. This paper discusses the current status of the NIC, the experimental steps needed toward achieving ignition and the steps required to demonstrate and enable the delivery of fusion energy as a viable carbon-free energy source.

Moses, E

2011-07-26T23:59:59.000Z

49

CRITICALITY CONTROL DURING THE DISMANTLING OF A URANIUM CONVERSION PLANT  

SciTech Connect

Within the Commissariat a l'Energie Atomique, in the Cadarache Research Center in southern France, the production at the Enriched Uranium Treatment Workshops started in 1965 and ended in 1995. The dismantling is in progress and will last until 2006. The decommissioning is planned in 2007. Since the authorized enrichment in 235U was 10% in some parts of the plant, and unlimited in others, the equipment and procedures were designed for criticality control during the operating period. Despite the best previous removing of the uranium in the inner parts of the equipment, evaluation of the mass of remaining fissile material by in site gamma spectrometry measurement shows that the safety of the ''clean up'' operations requires specific criticality control procedures, this mass being higher than the safe mass. The chosen method is therefore based on the mapping of fissile material in the contaminated parts of the equipment and on the respect of particular rules set for meeting the criticality control standards through mass control. The process equipment is partitioned in separated campaign, and for each campaign the equipment dismantling is conducted with a precise traceability of the pieces, from the equipment to the drum of waste, and the best final evaluation of the mass of fissile material in the drum. The first results show that the mass of uranium found in the dismantled equipment is less than the previous evaluation, and they enable us to confirm that the criticality was safely controlled during the operations. The mass of fissile material remaining in the equipment can be then carefully calculated, when it is lower than the minimal critical mass, and on the basis of a safety analysis, we will be free of any constraints regarding criticality control, this allowing to make procedures easier, and to speed up the operations.

LADURELLE, Laurent; LISBONNE, Pierre

2003-02-27T23:59:59.000Z

50

INERI-2006-003-F FY07 Annual Report  

SciTech Connect

Project Title: Comparison of Characterization Methods for Anisotropy and Microstructure of TRISO Particle Layers This INERI was created to support a comparative study between the newly developed two modulator generalized ellipsometry microscope (2-MGEM) at the Oak Ridge National Laboratory (ORNL) and the more traditional optical polarimeter (RAPAX) at the Commissariat l' nergie Atomique (CEA). These two systems are used to measure the anisotropy of the pyrocarbon layers in tri-isotropic (TRISO) coated particle fuel, which is an important parameter related to fuel performance. Although this project was only just started in June 2007, good progress has already been made. A kickoff meeting was held at ORNL on July 30-31, 2007 to present early progress and discuss details of the proposed work plan. This meeting was of great benefit to the participants, offering an opportunity to overcome the language barrier and more thoroughly communicate project relevant information. Each technical lead gave a presentation explaining the analysis techniques used in his task and presented data on early measurements of the German reference fuels. Plans were finalized regarding what work needed to be done and how to proceed with the comparative study. Possibilities for the inclusion of other coated particle samples, in addition to the two German reference fuels originally proposed, were also discussed. A list of these additional sample has now been generated and approved. Coating fragments from this series of different TRISO particle fuels have been sent from ORNL to the CEA and TEM analysis is in progress. Comparisons have already been made between the microstructure of the two German reference fuels which are the primary samples for this project. Specimens have also been prepared from the German reference fuels for comparative analysis between the 2-MGEM and RAPAX devices and initial measurements performed. Plans are to exchange specimens of the various fuel types in early FY08 for comparative analysis.

Hunn, John D [ORNL

2007-10-01T23:59:59.000Z

51

Neutron source capability assessment for cumulative fission yields measurements  

Science Conference Proceedings (OSTI)

A recent analysis of high-quality cumulative fission yields data for Pu-239 published in the peer-reviewed literature showed that the quoted experimental uncertainties do not allow a clear statement on how the fission yields vary as a function of energy. [Prussin2009] To make such a statement requires a set of experiments with well 'controlled' and understood sources of experimental errors to reduce uncertainties as low as possible, ideally in the 1 to 2% range. The Inter Laboratory Working Group (ILWOG) determined that Directed Stockpile Work (DSW) would benefit from an experimental program with the stated goal to reduce the measurement uncertainties significantly in order to make a definitive statement of the relationship of energy dependence to the cumulative fission yields. Following recent discussions between Lawrence Livermore National Laboratory (LLNL) and Los Alamos National Laboratory (LANL), there is a renewed interest in developing a concerted experimental program to measure fission yields in a neutron energy range from thermal energy (0.025 eV) to 14 MeV with an emphasis on discrete energies from 0.5 to 4 MeV. Ideally, fission yields would be measured at single energies, however, in practice there are only 'quasi-monoenergetic' neutrons sources of finite width. This report outlines a capability assessment as of June 2011 of available neutron sources that could be used as part of a concerted experimental program to measure cumulative fission yields. In a framework of international collaborations, capabilities available in the United States, at the Atomic Weapons Establishment (AWE) in the United Kingdom and at the Commissariat Energie Atomique (CEA) in France are listed. There is a need to develop an experimental program that will reduce the measurement uncertainties significantly in order to make a definitive statement of the relationship of energy dependence to the cumulative fission yields. Fission and monoenergetic neutron sources are available that could support these fission yield experiments in the US, as well as at AWE and CEA. Considerations that will impact the final choice of experimental venues are: (1) Availability during the timeframe of interest; (2) Ability to accommodate special nuclear materials; (3) Cost; (4) Availability of counting facilities; and (5) Expected experimental uncertainties.

Descalle, M A; Dekin, W; Kenneally, J

2011-04-06T23:59:59.000Z

52

Future Transient Testing of Advanced Fuels  

Science Conference Proceedings (OSTI)

The transient in-reactor fuels testing workshop was held on May 4–5, 2009 at Idaho National Laboratory. The purpose of this meeting was to provide a forum where technical experts in transient testing of nuclear fuels could meet directly with technical instrumentation experts and nuclear fuel modeling and simulation experts to discuss needed advancements in transient testing to support a basic understanding of nuclear fuel behavior under off-normal conditions. The workshop was attended by representatives from Commissariat à l'Énergie Atomique CEA, Japanese Atomic Energy Agency (JAEA), Department of Energy (DOE), AREVA, General Electric – Global Nuclear Fuels (GE-GNF), Westinghouse, Electric Power Research Institute (EPRI), universities, and several DOE national laboratories. Transient testing of fuels and materials generates information required for advanced fuels in future nuclear power plants. Future nuclear power plants will rely heavily on advanced computer modeling and simulation that describes fuel behavior under off-normal conditions. TREAT is an ideal facility for this testing because of its flexibility, proven operation and material condition. The opportunity exists to develop advanced instrumentation and data collection that can support modeling and simulation needs much better than was possible in the past. In order to take advantage of these opportunities, test programs must be carefully designed to yield basic information to support modeling before conducting integral performance tests. An early start of TREAT and operation at low power would provide significant dividends in training, development of instrumentation, and checkout of reactor systems. Early start of TREAT (2015) is needed to support the requirements of potential users of TREAT and include the testing of full length fuel irradiated in the FFTF reactor. The capabilities provided by TREAT are needed for the development of nuclear power and the following benefits will be realized by the refurbishment and restart of TREAT. •TREAT is an absolute necessity in the suite of reactor fuel test capabilities •TREAT yields valuable information on reactivity effects, margins to failure, fuel dispersal, and failure propagation •Most importantly, interpretation of TREAT experiment results is a stringent test of the integrated understanding of fuel performance.

Jon Carmack

2009-09-01T23:59:59.000Z

53

SILENE Benchmark Critical Experiments for Criticality Accident Alarm Systems  

SciTech Connect

In October 2010 a series of benchmark experiments was conducted at the Commissariat a Energie Atomique et aux Energies Alternatives (CEA) Valduc SILENE [1] facility. These experiments were a joint effort between the US Department of Energy (DOE) and the French CEA. The purpose of these experiments was to create three benchmarks for the verification and validation of radiation transport codes and evaluated nuclear data used in the analysis of criticality accident alarm systems (CAASs). This presentation will discuss the geometric configuration of these experiments and the quantities that were measured and will present some preliminary comparisons between the measured data and calculations. This series consisted of three single-pulsed experiments with the SILENE reactor. During the first experiment the reactor was bare (unshielded), but during the second and third experiments it was shielded by lead and polyethylene, respectively. During each experiment several neutron activation foils and thermoluminescent dosimeters (TLDs) were placed around the reactor, and some of these detectors were themselves shielded from the reactor by high-density magnetite and barite concrete, standard concrete, and/or BoroBond. All the concrete was provided by CEA Saclay, and the BoroBond was provided by Y-12 National Security Complex. Figure 1 is a picture of the SILENE reactor cell configured for pulse 1. Also included in these experiments were measurements of the neutron and photon spectra with two BICRON BC-501A liquid scintillators. These two detectors were provided and operated by CEA Valduc. They were set up just outside the SILENE reactor cell with additional lead shielding to prevent the detectors from being saturated. The final detectors involved in the experiments were two different types of CAAS detectors. The Babcock International Group provided three CIDAS CAAS detectors, which measured photon dose and dose rate with a Geiger-Mueller tube. CIDAS detectors are currently in use at Y-12 in the newly constructed Highly Enriched Uranium Materials Facility. The second CAAS detector used a {sup 6}LiF TLD to absorb neutrons and a silicon detector to count the charge particles released by these absorption events. Lawrence Livermore National Laboratory provided four of these detectors, which had formerly been used at the Rocky Flats facility in the United States.

Miller, Thomas Martin [ORNL; Reynolds, Kevin H. [Y-12 National Security Complex

2011-01-01T23:59:59.000Z

54

Technical Letter Report Assessment of Ultrasonic Phased Array Inspection Method for Welds in Cast Austenitic Stainless Steel Pressurizer Surge Line Piping JCN N6398, Task 1B  

SciTech Connect

Research is being conducted for the U.S. Nuclear Regulatory Commission (NRC) at the Pacific Northwest National Laboratory (PNNL) to assess the effectiveness and reliability of advanced nondestructive examination (NDE) methods for the inspection of light water reactor components. The scope of this research encompasses primary system pressure boundary materials including cast austenitic stainless steels (CASS); dissimilar metal welds; piping with corrosion-resistant cladding; weld overlays, inlays and onlays; and far-side examinations of austenitic piping welds. A primary objective of this work is to evaluate various NDE methods to assess their ability to detect, localize, and size cracks in coarse-grained steel components. In this effort, PNNL supports cooperation with Commissariat à l’Energie Atomique (CEA) to assess reliable inspection of CASS materials. The NRC Project Manager has established a cooperative effort with the Institut de Radioprotection et de Surete Nucleaire (IRSN). CEA, under funding from IRSN, are supporting collaborative efforts with the NRC and PNNL. Regarding its work on the NDE of materials, CEA is providing its modeling software (CIVA) in exchange for PNNL offering expertise and data related to phased-array detection and sizing, acoustic attenuation, and back scattering on CASS materials. This collaboration benefits the NRC because CEA performs research and development on CASS for Électricité de France (EdF). This technical letter report provides a summary of a technical evaluation aimed at assessing the capabilities of phased-array (PA) ultrasonic testing (UT) methods as applied to the inspection of welds in CASS pressurizer (PZR) surge line nuclear reactor piping. A set of thermal fatigue cracks (TFCs) was implanted into three CASS PZR surge-line specimens (pipe-to-elbow welds) that were fabricated using vintage CASS materials formed in the 1970s, and flaw responses from these cracks were used to evaluate detection and sizing performance of the PA-UT methods applied. This effort was comprised of multiple elements that included use of microstructural knowledge (dimensional analysis, grain orientation, and grain type) as well as sound field modeling to more effectively modify inspection parameters and enhance the inspection outcomes. Advanced probe design and sound field simulations were employed to enhance detection and characterization of circumferentially oriented flaws, and an assessment of lateral (circumferential) flaw localization capability and performance was also conducted. An evaluation of flaw detection, length sizing, depth sizing, and signal-to-noise ratio was performed for all flaws in the subject specimens, as a function of various inspection parameters, and finally, measurements were made to quantify and assess the baseline CASS material noise and its potential impact on flaw detection.

Diaz, Aaron A.; Cinson, Anthony D.; Crawford, Susan L.; Mathews, Royce; Moran, Traci L.; Anderson, Michael T.

2009-07-28T23:59:59.000Z

55

ART CCIM PHASE II-A OFF-GAS SYSTEM EVALUATION TEST REPORT  

SciTech Connect

AREVA Federal Services (AFS) is performing a multi-year, multi-phase Advanced Remediation Technologies (ART) project, sponsored by the U.S. Department of Energy (DOE), to evaluate the feasibility and benefits of replacing the existing joule-heated melter (JHM) used to treat high level waste (HLW) in the Defense Waste Processing Facility (DWPF) at the Savannah River Site with a cold crucible induction melter (CCIM). The AFS ART CCIM project includes several collaborators from AREVA subsidiaries, French companies, and DOE national laboratories. The Savannah River National Laboratory and the Commissariat a l’Energie Atomique (CEA) have performed laboratory-scale studies and testing to determine a suitable, high-waste-loading glass matrix. The Idaho National Laboratory (INL) and CEA are performing CCIM demonstrations at two different pilot scales to assess CCIM design and operation for treating SRS sludge wastes that are currently being treated in the DWPF. SGN is performing engineering studies to validate the feasibility of retrofitting CCIM technology into the DWPF Melter Cell. The long-term project plan includes more lab-testing, pilot- and large-scale demonstrations, and engineering activities to be performed during subsequent project phases. A simulant of the DWPF SB4 feed was successfully fed and melted in a small pilot-scale CCIM system during two test series. The OGSE tests provide initial results that (a) provide melter operating conditions while feeding a DWPF SB4 simulant feed, (b) determine the fate of feed organic and metal feed constituents and metals partitioning, and (c) characterize the melter off-gas source term to a downstream off-gas system. The INL CCIM test system was operated continuously for about 30 hours during the parametric test series, and for about 58 hours during the OGSE test. As the DWPF simulant feed was continuously fed to the melter, the glass level gradually increased until a portion of the molten glass was drained from the melter. The glass drain was operated periodically on-demand. A cold cap of unmelted feed was controlled by adjusting the feedrate and melter power levels to obtain the target molten glass temperatures with varying cold cap levels. Three test conditions were performed per the test plan, during which the melter was operated with a target melt temperature of either 1,250oC or 1,300oC, and with either a partial or complete cold cap of unmelted feed on top of the molten glass. Samples of all input and output streams including the starting glass, the simulant feed, the off-gas particulate matter, product glass, and deposits removed from the crucible and off-gas pipe after the test were collected for analysis.

Nick Soelberg

2009-04-01T23:59:59.000Z