DOCSLIB.ORG

Cermet Spent Nuclear Fuel Casks and Waste Packages

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Cermet Spent Nuclear Fuel Casks and Waste Packages Cermet Spent Nuclear Fuel Casks and Waste Packages Charles W. Forsberg and Leslie R. Dole Paper NN-8.8 Room Constitution A (Sheraton) Scientific Basis for Nuclear Waste Management XXX Materials Research Society Fall Meeting Boston, Massachusetts 11:00 AM; November 29, 2006 Oak Ridge National Laboratory* P.O. Box 2008, Oak Ridge, TN., 37831 United States of America E-mail: [email protected] GNS Storage and Transport Cask (Current Technology) OOAKAK R RIDGEIDGE *Notice: This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725 with the U.S. OAK RIDGE NATIONAL LABORATORY Department of Energy. The United States Government retains and the publisher, by accepting the article for NATIONALATIONAL L ABORATORYABORATORY U. S. DEPARTMENTN OF ENERGYL publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. File: DU Viewgraphs: MSR 06 Cermet 1 The United States and Russia have been Examining Cermet Spent Nuclear Fuel (SNF) Casks Storage, Transportation, and Waste Disposal • Multiyear program • Several factors have created an interest in cermet casks − New fabrication methods − More emphasis on physical protection − The availability of depleted uranium dioxide (DUO2) − An understanding of how waste package (WP) composition can improve repository performance • Paper summarizes results • References in the paper to the detailed reports GNS Storage and Transport Cask OAK RIDGE NATIONAL LABORATORY (Current Technology) U. S. DEPARTMENT OF ENERGY 2 Cermets Combine the Best Properties of Ceramics and Metals Ceramics: Shielding, Hardness, etc.; Metals: Strength, Ductility, etc. Cermets Are Used for Cermet-Body Cross Section Demanding Applications Clean Steel Ceramics -Armor (Al2O3, Brake Shoes SiC) - Neutron Shielding (DUO2, Gd2O3) - Gamma Shielding (DUO2) Metal Matrix Main Battle - Strength Tank Armor Cask Body - Thermal Conductivity Cutting Tools OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 04-070 3 Outline: Cermet Casks • System applications • Shielding performance • Assault protection • Repository performance − Optimized geochemical environment − Neptunium and technetium sorption − Nuclear criticality • Depleted uranium (DU) disposal • Co-disposal of SNF and DU • Fabrication • Conclusion OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 4 System Applications OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 5 Cermet Casks have Multiple Applications Overpack for Transportation, Aging, and Disposal (TAD) Canister; Shielded TAD; Component of WP Dry Store Transport Repository Disposal (At Reactor) Cask Removable Repository Overpack Overpack (2 cm C-22) Transport Surface Facility Overpack Cask Minimal Facility No SNF Shuffle (Surface Store SNF for Heat Management) Underground Overpack Functions (Intact Package) Storage: Heat Removal No Remote Operations Transport: Accident Protection Redundant/Alternative Barrier Disposal: 10,000 year lifetime OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 03-1476 Shielding Performance OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 7 DUO2-Steel Cermets are High- Performance SNF Casks • Maximize number of SNF assemblies based on − Maximum allowed cask weight − Maximum allowed cask diameter • Cermet construction − Steel matrix • Strength • High-thermal conductivity − DUO2 ceramic • Shielding • Repository compatible − No concrete − No RCRA metals (lead) − No organics − Cost constraints (no tungsten) − No reactive metals (uranium metal) OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY ORNL DWG 2001-221 8 Assault Protection OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 9 Cermet Casks can have Extraordinary Resistance to Assault • Cermets are a traditional form of tank armor − Ceramic breaks up shaped charge or penetrator − Metal absorbs the energy • SNF Casks are heavy relative to military tanks − Main battle tank: 70 tons and large − SNF rail cask: 100 tons and much smaller German Rail Gun for Testing Casks: 1 Ton Projectile at 300 m/s OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 10 Repository Performance OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 11 Cermet WPs (Fe and DUO2) may Offer Superior SNF Waste Isolation • Cermet WP composition (metals and ceramics) chosen to limit radionuclide migration • Multiple mechanisms for better performance − Control of geochemical environment − Neptunium and technetium sorption − Nuclear criticality control OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 12 Uranium Oxide and Metallic Iron Deposits have Slow Water Flow, Gas Diffusion, and Oxidation Natural UO2 Ore Deposits Roman Nail Deposits 280 Boltwoodite 6+ K(U O ) ()SiO (OH) . 4H O S 2 223 2 2 2 S A Uranophane M 240 6+ . T I Ca (U O2)6H2 Si 2O7 2O N U R Oxidizing E 200 Intact P Schoepite Groundwater Nails L 6+ A . (Iron) 3 UO3 2H 2O R E (cm /kg) N 160 I Soddyite M 6+ UO3 . Hydrated F ()U O SiO 2H O 242 2 Iron Oxide O Uraninite U O E 120 38 M 4+ 6+ U (OU1-XU) X 2+X L O UO2 V 80 Cermet WPs Slow Radionuclide Migration EVOLUTION OF URANIUM OXIDE UNDER OXIDIZING GROUNDWATER CONDITIONS by Similar Mechanisms OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 13 Uranium Oxides Slow Release of Neptunium and Technetium • Experimental data indicates uranium oxides slow radionuclide migration − Neptunium − Technetium (less data) • EPRI analysis indicates major impact on Yucca Mountain (YM) performance • Added DU should provide further benefits EPRI YM Assessment OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 14 DU Cermet Casks Reduce Long-Term Criticality Issues in the Repository Cf-251 902 y • Most fissile isotopes decay to longer- SCML = 5 g Bk-247 lived uranium isotopes before large- 1400 y Cm-243 Cm-247 scale WP failure 29 y 15.6x106 y SCML = 90 g SCML = 900 g EC Am-243 99.8% • Long-term repository criticality issues 0.2% 7370 y SCML = 25,000 g are 235U and 233U Pu-239 Pu-243 3 24.1x10 y 4.96 h 235 6 SCML = 450 g − U: T1/2 = 700 · 10 years Np-239 233 5 2.35 d − U: T = 1.6 · 10 years CM = No 1/2 U-235 U-239 700x106 y 23.5 m SCML = 700 g • DU in cermet WP isotopically dilutes Pa-231 32.5x103 y CM = Yes SNF uranium fissile isotopes (>3 tons Th-231 25.5 h DU per ton of SNF) • Average WP enrichment: <<1% Actinide Decay Chain OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 15 Depleted Uranium Disposal OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 16 WPs Provide a DU Disposal Pathway • World inventory ~106 tons DU • Hazardous − Alpha: ~100s nCi/g − Toxic heavy metal • Repository use − Cermet WP • Engineered barrier • Beneficial use − Safe disposal Paducah Gaseous Diffusion Plant Cylinder Storage of DU (14-ton Containers) OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 17 Co-Disposal of SNF and DU OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 18 Cermet WPs Enable Co-Disposal and Co-Recovery of DU and SNF The Future is Uncertain; if the Future Adopts a Closed Fuel Cycle, the WP has the SNF and DU OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 19 Fabrication OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 20 Cermet Fabrication • Cermets are extraordinary materials; but − Difficult to fabricate − Almost impossible to weld • Cermet SNF cask viability depends upon economic fabrication methods • Three viable fabrication methods examined − Forged cermet cylinder (FCC) process − Cermet extrusion section (CES) process − Casting • CES process is the currently preferred option − Lowest front-end capital equipment cost − Fewer uncertainties − Allows for variable-composition cermet OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 21 Cermet Extrusion Section Process Steel/DUO2 Particulate Fill Extrude Section Add Particulate Die Fill to Can Hydraulic Compress Can Layer Ram Add Next Powder Press Layer (Hot) Compact Fill Machine Extrusions Seal Preform, Cermet Heat, and Degas Extrusion Assemble Cask Steel Can (Braze or Weld) Inner Cask Wall Powder Mix Outer Cask Wall Not to Scale Heat and Degas OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 06-010 22 Conclusions • International consortium has examined cermet cask options • Cermet casts are technically viable − Preliminary economic analysis is favorable • Cermet cask system can integrate − SNF physical protection − SNF storage − SNF transport − Integrated SNF and DU disposal • Significant R&D remains OAK RIDGE NATIONAL LABORATORY U. S. DEPARTMENT OF ENERGY 23 Abstract Cermet Spent Nuclear Fuel Casks and Waste Packages Scientific Basis for Nuclear Waste Management XXX; Materials Research Society Fall Meeting Boston, Massachusetts; November 30, 2006 Charles W. Forsberg and Leslie R. Dole Oak Ridge National Laboratory; P.O. Box 2008, Oak Ridge, TN., 37831 E-mail: [email protected] Multipurpose transport, aging, and disposal casks are needed for the management of spent nuclear fuel (SNF). Self-shielded cermet casks can outperform current SNF casks because of the superior properties of cermets, which consist of encapsulated hard ceramic particulates dispersed in a continuous ductile metal matrix to produce a strong high-integrity, high-thermal- conductivity cask. A multiyear, multinational development and testing program has been developing cermet SNF casks made of steel, depleted uranium dioxide, and other materials. Because cermets are the traditional material of construction for armor, cermet
Load more

Recommended publications
  • Microwave Sintering of Alumina-Titanium Cermets Redacted for Privacy Abstract Approved: (
    AN ABSTRACT OF THE THESIS OF Wendell R. Wrzesinski for the degree of Master of Material Science in Mechanical Engineering presented on 10-19-87. Microwave Sintering of Alumina-titanium Cermets Redacted for Privacy Abstract Approved: ( The influence of microwave radiation on the fabrication of cermet materials has been investigated for alumina-titanium cermets with compositions ranging from 20 to 80 wt. % titanium. An industrial microwave oven was characterized and adapted to process cermet materials. Physical and mechanical property determinations were made as a function of microwave processing time and compared to a furnace sintered sample. Electron microscopy was conducted on the composite materials in evaluat- ing the extent of bonding between metal and oxide particles and particle sizing in the cermet. Sintering of composite materials through microwave radiation usagemay be possible as a reduced cost, time-saving, processing technique. Microwave Sintering of Alumina-titanium Cermets by Wendell R. Wrzesinski A THESIS submitted to Oregon State University in partial fulfillment of the requirements for the degree of Master of Material Science Completed: 10-19-87 Commencement June 1988 APPROVED: Redacted for Privacy Profesqr of Material Science and Engineering incharge of major Redacted for Privacy head of department of MechanicalEngineering Redacted for Privacy Dean of Grad School Date thesis presented: 10-19-87 ACKNOWLEDGEMENT The author would like to sincerely thank Dr. JimRawers and Rick Wilson for their assistance and guidance inexperimentation and preparation involved with this thesis, the Bureau ofMines for its support, and those others who offered invaluableassistance including: Dr. Jim Rawers, Kellee Roub, and Rick Wilsonfor technical review of this manuscript, Dan Davis forpreparing furnace sintered materials, Keith Collins formicroscopic eval- uation, and Earl Peterson and Steve Anderson fortheir drafting and photography.
    [Show full text]
  • Nasa Tm X-3265 17 Effect of Magnesium Oxide Content
    NASA TECHNICAL. NASA TM X-3265 17 MEMORANDUM CO 1 I b- ; X in.l rui LOAN COPY: RE t-1! AFWL TECHNICAL t-1: KIRTLAND AFB EFFECT OF MAGNESIUM OXIDE CONTENT ON OXIDATION BEHAVIOR OF SOME SUPERALLOY-BASE CERMETS Isidor Zaplatynsky Lewis Research Center Cleveland, Ohio 44135 \ NATIONAL AERONAUTICS AND SPACE ADMINISTRATION • WASHINIGTUlUILJD.G - • AUGUST 1975 ERRATA NASA Technical Memorandum X-3265 EFFECT OF MAGNESIUM OXIDE CONTENT ON OXIDATION BEHAVIOR OF SOME SUPERALLOY-BASE CERMETS by Isidor Zaplatynsky August 1975 The composition of the alloy listed as Hastelloy X in table I, page 9, does not fit the specifications for HASTELLOY ® (a registered trademark of the Cabot Corporation) alloy X. Further, an analysis of this alloy indicated deviation from the specifications shown in table I. The following corrected table shows the correct analysis of this alloy, henceforth called Alloy A. Thus, throughout the report, references to Hastelloy X should be read to mean Alloy A. Further, references to Inconel-702 should be read to meanlNCONEL ® alloy 702. ERRATA NASA Technical Memorandum X-3265 EFFECT OF MAGNESIUM OXIDE CONTENT ON OXIDATION BEHAVIOR OF SOME SUPERALLOY-BASE CERMETS by Isidor Zaplatynsky August 1975 The composition of the alloy listed as Hastelloy X in table I, page 9, does not fit the specifications for HASTELLOY © (a registered trademark of the Cabot Corporation) alloy X. Further, an analysis of this alloy indicated deviation from the specifications shown in table I. The following corrected table shows the correct analysis of this alloy, henceforth called Alloy A. Thus, throughout the report, references to Hastelloy X should be read to mean Alloy A.
    [Show full text]
  • Repository Criticality Control with Depleted-Uranium-Dioxide Cermet Waste Packages
    —Summary— REPOSITORY CRITICALITY CONTROL WITH DEPLETED-URANIUM-DIOXIDE CERMET WASTE PACKAGES Charles W. Forsberg Oak Ridge National Laboratory* P.O. Box 2008 Oak Ridge, Tennessee 37831-6180 Tel: (865) 574-6783 Fax: (865) 574-9512 Email: [email protected] File Name: Cermet.DuCermet.Criticality Session: Geological Disposal Prepared for Session: Geological Disposal Embedded Topical Meeting on Practical Implementation of Nuclear Criticality Safety American Nuclear Society Reno, Nevada November 11–15, 2001 Limit: 1000 words Actual: 823 words The submitted manuscript has been authored by a contractor of the U.S. Government under contract DE-AC05-00OR22725. Accordingly, the U.S. Government retains a nonexclusive, royalty-free license to publish or reproduce the published form of this contribution, or allow others to do so, for U.S. Government purposes. _________________________ *Oak Ridge National Laboratory, managed by UT-Battelle, LLC, for the U.S. Department of Energy under contract DE-AC05-00OR22725. REPOSITORY CRITICALITY CONTROL WITH DEPLETED URANIUM DIOXIDE CERMET WASTE PACKAGES It is proposed that the structural components and internal basket structures of spent nuclear fuel (SNF) waste packages (WPs), which will be sequestered with the SNF at the repository, be constructed of depleted uranium dioxide (DUO2 )–steel cermets. The cermet used for the WP basket would also contain neutron absorbers with high-absorption-cross-sections such as boron or rare earth oxides. This strategy would provide both operational and long-term (repository post-closure) criticality control. As the WP degrades, the 238U in the depleted uranium (DU) would mix with the degrading SNF and isotopically dilute 233U and 235U to levels (<1 wt % 235U in 238U; <0.66 wt % 233U in 238 U) that ensure critically will not occur.
    [Show full text]
  • Additive Manufacturing of Ceramics and Cermets: Present Status and Future Perspectives
    Sådhanå Ó (2021) 46:162 Indian Academy of Sciences https://doi.org/10.1007/s12046-021-01685-2Sadhana(0123456789().,-volV)FT3](0123456789().,-volV) Additive manufacturing of ceramics and cermets: present status and future perspectives MAINAK SAHA1,2,* and MANAB MALLIK1,* 1 Department of Metallurgical and Materials Engineering, National Institute of Technology, Durgapur 713209, West Bengal, India 2 Department of Metallurgical and Materials Engineering, Indian Institute of Technology, Madras 600036, Tamil Nadu, India e-mail: [email protected]; [email protected] MS received 6 November 2020; revised 19 May 2021; accepted 6 July 2021 Abstract. The present decade has witnessed a huge volume of research revolving around a number of Additive Manufacturing (AM) techniques, especially for the fabrication of different metallic materials. How- ever, fabrication of ceramics and cermets using AM-based techniques mainly suffers from two primary limi- tations which are: (i) low density and (ii) poor mechanical properties of the final components. Although there has been a considerable volume of work on AM based techniques for manufacturing ceramic and cermet parts with enhanced densities and improved mechanical properties, however, there is limited understanding on the cor- relation of microstructure of AM-based ceramic and cermet components with the mechanical properties. The present article is aimed to review some of the most commonly used AM techniques for the fabrication of ceramics and cermets. This has been followed by a brief discussion on the microstructural developments during different AM-based techniques. In addition, an overview of the challenges and future perspectives, mainly associated with the necessity towards developing a systematic structure-property correlation in these materials has been provided based on three factors viz.
    [Show full text]
  • Some Neutron and Gamma Radiation Characteristics of Plutonium Cermet
    Some Neutron and Gamma Radiation Characteristics of Plutonium Cermet Fuel for Isotopic Power Sources R. A. NEFF, M. E. ANDERSON, A. R. CAMPBELL, and F. X. HAAS Mound Laboratory, Miamisburg, Ohio* Gamma and neutron measurements on various types of plutonium sources are presented in order to show the effects of ZTO, ZSO, ZSF, S3SPu, age of the fuel, and size of the source on the gamma and neutron spectra. Analysis of the radiation measurements shows that fluorine is the main contributor to the neutron yields from _resent plutonium-molybdenum cermet fuel while both fluorine and s Spu daughters contribute significantly to the gamma-ray intensities. Plutonium-238 has many desirable qual- The fuel used in heat sources is nomi- ities for a radioisotopic heat source fuel nally about 80% a=SPu, 16% _SgPu, and 1.2 and has been used in numerous heat sources ppm =36Pu. The _39Pu contributes a group for terrestrial, marine and space applica- of peaks around 400 keV while the main tions. The plutonium fuel has been pre- contributions from _3SPu are the two in- pared in several different forms depending tense peaks at 2614 and 583 keV due to on the requirements of the particular mis- the =°STI daughter. Other peaks from a3ePu sion and the technology available at the daughters which can be seen in this spec- time of fabrication. Fuel forms used in trum are the 510 and 860 keV peaks also the past have been plutonium metal, alloys, from S°STl, the 240 and 301 keV peaks from and dioxide microspheres. The most recent _1sPb, and the 727 and 1620 keV peaks from fuel form to be used is plutonium,molybde- SZ2Bi.
    [Show full text]
  • Microstructure and Mechanical Properties of Multicomponent Metal Ti(C,N)-Based Cermets
    metals Article Microstructure and Mechanical Properties of Multicomponent Metal Ti(C,N)-Based Cermets Xuelei Wang 1,* , Qiufeng Wang 2, Zhaojun Dong 3, Xiaoqian Zhou 1, Xiaoliang Wang 1, Boyan Zhang 1 and Chao Meng 1,* 1 College of Materials Science and Engineering, Liaoning Technical University, Fuxin 123000, China; [email protected] (X.Z.); [email protected] (X.W.); [email protected] (B.Z.) 2 School of Geomatics, Liaoning Technical University, Fuxin 123000, China; [email protected] 3 College of New Energy and Environment, Jilin University, Changchun 130012, China; [email protected] * Correspondence: [email protected] (X.W.); [email protected] (C.M.); Tel.: +86-0418-511-0099 (X.W.); +86-0418-511-0102 (C.M.) Received: 7 June 2020; Accepted: 8 July 2020; Published: 10 July 2020 Abstract: Ti(C,N)-based cermets with multicomponent ingredients were prepared using vacuum sintering technology. The effect of molding agents, binder phase and sintering temperature on Ti(C,N)-based cermets were studied. The optimum molding performance was obtained by adding 2% polyvinyl alcohol (PVA-1788). The microstructure and mechanical properties of Ti(C,N)-based cermets were investigated. The Ti(C,N)-based cermet with a weight percentage of TiC:TiN:Ni:Co:Mo:WC:Cr3C2:C = 40:10:20:10:7:8:4:1 and sintered at 1450 ◦C had the optimal mechanical properties. The relative bending strength, Vickers hardness, elastic modulus and wear resistance were 2010 MPa, 15.01 GPa, 483.57 GPa and 27 mg, respectively. Additionally, X-ray diffraction (XRD), backscatter scanning electron microscopy pictures (SEM–BSE), energy dispersive spectrometry (EDS) and optical micrographs of Ti(C,N)-based cermets were characterized.
    [Show full text]
  • Cermet Fuel Element
    CERMET FUEL ELEMENT (FE) ON THE BASIS OF MICROFUEL – FE PROTOTYPE FOR FUTURE POWER ENGINEERING I.I.Fedik, V.P.Deniskin, V.I.Nalivaev S.S.Gavrilin FSUE “SRI SIA “Luch” The FE with ceramic fuel and cladding of E110 alloy under average impletion depth of 43-45MW day/kg U with providing of 3 and 4 year operation periods are used successfully in VVER. The program had been developed for improving of the fuel cycles economical indexes and for further increasing the VVER operational characteristics. In this program the reactor safety increasing has been foreseen and also the coefficient of capacity using (KIUM) has at the expense of the average implement of 55-60 MW day/kg U achieving. The program foresees also the integration of 5-6 year fuel cycle and other developments [1,2]. It is planning to solve the pointed problems with help of traditional technical solution, directed to the improving of FE with ceramic fuel. In the present paper the design-engineering and experimental development results have been presented for creation of cermet FE on the basis of micro-fuel with matrix structure (in the further -the cermet FE) for VVER. The works have been carried out over period of the last 10 years in SRI SIA “Luch” jointly with” OKB “Gidropress”, VSRINM Bochvar name, RNTs “Kurchatovsky institute,” FEI and other. The construction description. Cermet FE is differed from FE with ceramic fuel and from known dispersion type FE by following (Fig. [3,4]): cermet fuel core has matrix structure, excluding the contacts between fuel particles of 500 micron size at the nuclear fuel volume part in the composition of 79%; in the capacity of matrix material the alloy on the basis of Zr is used; between the cladding and the core the precoat of type silumin material is placed, providing the metallurgy adhesion and high heat conductivity.
    [Show full text]
  • INERT MATRIX — CERMET FUELS: TOWARD OPTIMIZED UTILISATION of Pu in a PWR NEUTRONIC STUDIES — the TANOX EXPERIMENT
    INERT MATRIX — CERMET FUELS: TOWARD OPTIMIZED UTILISATION OF Pu IN A PWR NEUTRONIC STUDIES — THE TANOX EXPERIMENT J. PORTA, J.Y. DORIATH, S. BALDL B. GUIGON Centre d etudes nucleaires de Cadarache, XA9953271 Saint-Paul-lez-Durance Ph. DEHAUDT, A. MOCELLIN Centre d'etudes nucleaires de Grenoble, Grenoble C. AILLAUD Centre d'etudes nucleaires de Cadarache, Saint-Paul-lez-Durance France Abstract In order to address the new issues linked to the checking of the nuclear programme and the abandonment of the fast reactor system in France, the Nuclear Reactor Division (DRN) of the CEA launched a study programme with the aim of increasing the plutonium load in pressurized water reactors. INTRODUCTION The nuclear industry landscape has considerably changed since the 1960s: the development of the fast breeder reactor system was first curtailed, then progressively left in abeyance, which resulted in the accumulation of large amounts of plutonium. A temporary solution for these stocks of plutonium consisted in using them in pressurized water reactors (PWRs). However, for safety reasons, essentially related to the great sensitivity of the cores of these reactors - due to a very negative moderating coefficient that makes cold hazards particularly difficult to control -, the safety authorities decided to limit core loading of Pu in its conventional, MOX (Mixed Oxide) form to only 30 %. On the other hand, for reasons linked to proliferation resistance and economics, increased burnup of these fuels is highly desirable. Although 20 reactors of the French nuclear power plants are authorized to operate with a load of 30 % MOX, only 17 currently use this fuel, while eight units are soon to receive authorization to operate using this fuel.
    [Show full text]
  • D3.5 Characterization of Sintered Ceramic and Cermet Parts
    Ref. Ares(2017)6114712 - 13/12/2017 D3.5 Version: 1.0 Date: 10.07.2017 Scheduled for: month 30 Author: LITHOZ Dissemination level: PU Document reference: D3.5 Provide characterization of sintered ceramic and cermet parts Project acronym: ToMax Project name: Toolless Manufacturing of Complex Structures Call: H2020-FoF-2014 Grant agreement no.: 633192 Project duration: 36 months (2015-01-01 – 2017-12-31) Project coordinator: TUW (Technische Universität Wien) Partners: (lead) Partner LITHOZ Project no. 633192 "Toolless Manufacturing of Complex Structures" ToMax H2020-633192 ToMax D3.5v1.0 FoF-02-2014 "Manufacturing processes for complex structures and geometries with efficient use of material" D3.5 Provide characterization of sintered ceramic and cermet parts Due date of deliverable: 2017-06-30 Actual submission date: 2017-07-10 Start date of project: 2015-01-01 Duration: 36 months Lead partner for this deliverable: Partner LITHOZ Project founded by the European Commission within the Horizon 2020 Programme Dissemination Level PU Public X CO Confidential, only for members of the consortium (including the Commission Services) D3.5 - Characterization of sintered parts Page 2 of 12 H2020-633192 ToMax D3.5v1.0 History chart Version Author Date Status Reviewer 1.0 Martin 2017-06-22 Schwentenwein 2017-07-10 final Koch Abstract The subject of this deliverable is the characterization of the 3D printed ceramic (alumina and sialon) and cermet (alumina-molybdenum) parts that have been developed in the course of Tomax. For the sintered alumina ceramics it could be demonstrated that it is possible to fabricate fully dense objects with maximum wall thickness of > 10 mm in the green and 10 mm in the sintered state without any defects.
    [Show full text]
  • Fabrication of Tic-20Mass%Ni Cermet Using MA-PCS Process
    Materials Transactions, Vol. 47, No. 10 (2006) pp. 2561 to 2565 #2006 The Japan Institute of Metals Fabrication of TiC-20 mass%Ni Cermet Using MA-PCS Process Keizo Kobayashi and Kimihiro Ozaki Materials Research Institute for Sustainable Development, National Institute of Advanced Industrial Science and Technology, Nagoya 463-8560, Japan Mechanical alloying and pulsed-current sintering were used to synthesize TiC-20 mass%Ni cermet with ultra-fine TiC particles dispersed. The mixture, in which Ti and Ni elements were uniformly distributed, was prepared by mechanical alloying of Ti, Ni and graphite powders for 18 ks. TiC particles were produced in the mixture milled for longer than 18 ks through a combustion synthesis reaction during heating. Mechanically alloyed Ti-C-Ni composite powder milled for 18 ks was consolidated using pulsed-current sintering at 1223 K under 70 MPa pressure. The sintered compact consisted of TiC and Ni. The average grain size of TiC particles in the sintered body was 0.80 mm. The relative density of the sintered compact reached 92% of the theoretical one; its Vickers hardness was 2260 Hv. [doi:10.2320/matertrans.47.2561] (Received April 17, 2006; Accepted August 25, 2006; Published October 15, 2006) Keywords: mechanical alloying, pulsed-current sintering, cermet alloy, TiC-20 mass%Ni, combustion synthesis reaction, ultra-fine particle 1. Introduction 2. Experimental Procedure TiC-based cermet alloys are utilized for high-performance Using planetary ball milling for 18 and 36 ks, TiC-20 cutting tools because of their high hardness and chemical mass%Ni powders were synthesized from starting materials stability.
    [Show full text]
  • 3D Gel Printing of Graded Tic-High Manganese Steel Cermet
    J Mater Sci (2019) 54:2122–2132 CompositesCOMPOSITES 3D gel printing of graded TiC-high manganese steel cermet Xinyue Zhang1, Leichen Guo2, Fang Yang1,* , Alex A. Volinsky3, Megan Hostetter3, and Zhimeng Guo1,* 1 Institute for Advanced Materials and Technology, University of Science and Technology Beijing, Beijing 100083, China 2 School of Engineering Technology, Purdue University, West Lafayette, IN 47907, USA 3 Department of Mechanical Engineering, University of South Florida, Tampa, FL 33620, USA Received: 13 July 2018 ABSTRACT Accepted: 20 September 2018 A new solid freeform process, 3D gel printing (3DGP), was proposed for Published online: designing and manufacturing graded composites. As an example, TiC-high 26 September 2018 manganese steel cermet with a gradient distribution of TiC was successfully designed and fabricated by 3DGP. The rheological behavior and polymerization Ó Springer Science+Business of slurries with different TiC content have been researched. The complex- Media, LLC, part of Springer shaped green bodies were printed accurately by depositing slurries layer by Nature 2018 layer. The scanning electron microscopy and X-ray diffraction revealed the gradient distribution and morphology of the TiC particles within a sintered sample. The density, hardness, abrasion wear resistance, transverse rupture strength and impact toughness of the 3D gel-printed TiC-high manganese steel cermet appeared graded distribution corresponding to its gradient structure. Gradient distribution of the composition, microstructure and mechanical properties of the 3D gel-printed part are consistent with the design concept. Results indicated that 3DGP is a promising approach for high-throughput design and fabrication of complex-shaped graded composites. Introduction requirements within a component.
    [Show full text]
  • Ti (C, N) Titanium Carbonitride Based Cermet Rods Ticn Based Cermet with Coolant Hole Cermets Blank of CNC Cutting Tools Materials
    Ti (C, N) Titanium carbonitride based cermet rods ticn based cermet with coolant hole cermets blank of CNC cutting tools materials Ti (C, N) Titanium carbonitride based cermet rods ticn based cermet with coolant hole cermets blank of CNC cutting tools materials was measured using a metal carbon titanium, tungsten, cobalt, nickel and other metals and metal carbide powder produced by powder metallurgy method ceramic materials, hardness up HRA91-93.5, density 6.45g / cm3, is an ideal high-speed CNC tool material, mainly used in high-speed CNC machining tool, provides a perfect solution for high-speed CNC machining, Very suitable for machining difficult to machine materials, particularly high-speed machining of titanium alloys in aircraft manufacturing, processing speeds of up to 300-350 m / min, the workpiece surface finish can be a mirror effect.this product is the company's patented product, patent number: 201210087901X. 1. Advantage Cermet CNC cutting tools toughness higher than ceramic tools,More wear-resistant than carbide cutting speed faster,metal ceramics have excellent surface polishing technology and high speed machining technology.With high-speed finishing and milling technology for low-carbon steel, carbon steel, alloy steel and stainless steel,to achieve superb turning, groove, boring, bearings and milling level.Having chipping resistance and wear resistance superior cermet.Having excellent thermal conductivity and wear resistance, is steel processing the best choice,suitable for steel turning, groove, boring, bearings and milling.Covering a wide range of steel finishing to roughing field. 2. High wear resistance Cermet hardness is higher than sintering carbide material, compared with the carbide, in high temperature conditions and ferrous metal processing work-pieces affinity is low, can obtain better surface finish, from low speed to high speed machining is possible.
    [Show full text]