RRFM 2009 Transactions - European Nuclear Society

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It is known since the early days of metallic fuel element development that an oxide layer at the interface Uranium-Aluminum prevents the formation of a diffusion layer very effectively [9]. Also in UMo-Al test fuel plates irradiated in-pile an oxide layer around the UMo particles has proven its effectiveness [14]. Furthermore, Nb, Ta, Ti or Zr has been proposed as a diffusion barrier [14, 15, 16]. d) Any combination of a), b) and c) e) Usage of a completely different matrix material, such as Magnesium. In 2006 it has been shown that it is possible to emulate the IL growth during in-pile irradiation of UMo/Al specimens by out-of-pile irradiation with 127 Iodine at 80 MeV. Typical burn-up fission densities are achieved within a few hours [17,18]. Because the energy of the ions usually is far below the Coulomb barrier the UMo samples are not activated during heavy ion irradiation. They are therefore easily accessible with normal laboratory equipment (SEM, EDX, and XRD). Since then, considerable progress has been made to improve the reliability of this method. In collaboration with CEA-Cadarache, TUM has build up a complete new irradiation setup at the tandem accelerator in Garching (Maier-Leibnitz Laboratorium) which allows monitoring and controlling the irradiation conditions like flux, fluency, vacuum and sampling temperature automatically. The new setup allows the quick irradiation of different kinds of samples [19]. Consequently, we decided to start an irradiation campaign at the tandem accelerator in Garching to screen as many combinations of the materials mentioned above as reasonably possible. For the irradiations UMo powder dispersed in an Aluminum matrix has been chosen. The results are also valid for the here described monolithic fuel development program, because anyhow the interaction between Al matrix, IL and UMo will be the focus of our characterization. We decided to divide the options mentioned into three parts (compare Tab. 2). For each option, one miniplate (in total 20) has been provided by AREVA-CERCA. The first part consists of atomized U7wt%Mo powder dispersed in an Al matrix with and without addition of secondary elements. 2wt%Si, 5wt%Si and 7wt%Si have been chosen as addition to the Al matrix to find the best Silicon concentration. Furthermore, 2wt%Ti, 2wt%Bi and 5wt%Bi have been added to the Al matrix, respectively, to check the positive effect of these elements. It has been reported, that the addition of Magnesium to Aluminum accelerates the diffusion at the U-Al interface [8]. In consequence, 2wt%Mg has been added to the matrix to check this effect. In each case the samples have been prepared with and without an oxide layer (UO 2 ) of ~2µm thickness around the UMo particles, to check its effectiveness as a diffusion barrier – second part. The third part consists of ternary U8wt%Mo-x ground powder dispersed in a pure Aluminum matrix. To study the principal effect of alloying the UMo, 1wt%Ti, 1,5wt%Nb, 3wt%Nb and 1wt%Pt have been added. One miniplate consisted of UMo dispersed in Magnesium, covered with AlFeNi. It was not possible to prepare a sample for irradiation from this miniplate. The meat was grayish and very brittle. It broke apart during cutting and polishing. It was not possible to obtain UMo particles coated with metals like Ta or Ti to check the impact of those elements on the formation of the diffusion layer during bombardment with heavy ions. However, examinations on this issue are planned on monolithic UMo/Al layer systems that will be prepared with the newly installed sputtering device. From the 20 miniplates provided by AREVA-CERCA 60 samples have been prepared for irradiation with 127 Iodine at 80 MeV. First irradiations have been performed since fall 2008 with an integral of 1x10 17 ions/cm² for each sample. This corresponds to a full burn-up of a 18 of 455
high flux research reactor. The irradiation temperature was ~200°C. The irradiation campaign will be finished until summer <strong>2009</strong>. Examinations on already irradiated samples are ongoing. The full set of data will be available until end of <strong>2009</strong>. . Sample Nr. Alloy Matrix Comment MAFIA-I-1 * U-7Mo Al-atomized Reference specimen MAFIA-I-2 * U-7Mo-ox Al-atomized MAFIA-I-3 * U-7Mo Al98-Si2 MAFIA-I-4 * U-7Mo-ox Al98-Si2 MAFIA-I-5 * U-7Mo Al95-Si5 Different Si concentrations to find the MAFIA-I-6 * U-7Mo-ox Al95-Si5 best concentration MAFIA-I-7 * U-7Mo Al93-Si7 MAFIA-I-8 U-7Mo-ox Al93-Si7 MAFIA-I-9 U-7Mo Al98-Mg2 MAFIA-I-10 U-7Mo-ox Al98-Mg2 MAFIA-I-11 U-7Mo Al98-Ti2 MAFIA-I-12 U-7Mo-ox Al98-Ti2 MAFIA-I-13 U-7Mo Al98-Bi2 MAFIA-I-14 U-7Mo-ox Al98-Bi2 MAFIA-I-15 U-7Mo Al95-Bi5 MAFIA-I-16 U-7Mo-ox Al95-Bi5 MAFIA-I-17 U-7Mo Mg MAFIA-I-18 U-7Mo-1Ti Al-ground MAFIA-I-19 U-7Mo-1,5Nb Al-ground MAFIA-I-20 U-7Mo-3Nb Al-ground MAFIA-I-21 U-7Mo-1Pt Al-ground Mg accelerates formation of IDL. Reproduction of this effect. Study the effect of Ti on IDL formation Different Bi concentrations to find the best concentration Mg matrix, did not work, brittle matrix, matrix with no adhesion to cladding To study principal effect of alloying the UMo on formation of IDL. Tab 2: List of mini-plates provided by AREVA-CERCA for heavy-ion irradiation. The irradiation has been completed for miniplates earmarked with (*). 3.2 Sputtering techniques The sputtering process offers the advantage, that perfect layers from any material can be grown on any substrate in any size. This means to the first, that monolithic full size foils and blank sheets from any given UMo alloy can successfully be produced. It means to the second, that a given UMo foil or blank sheet can be surrounded with a layer of any desired material, be it as a diffusion barrier or as a cladding. It means to the third, that bonding between the different layers is not a problem at all, because the layers will have the maximum physically possible adhesion to each other. On laboratory scale the sputtering technique provides the opportunity to quickly produce small numbers of high quality full size fuel plates for irradiation tests and further examinations, which is our primary aim. The applicability of sputtering to industrial scale seems promising but has to be further examined. Over the last two years TUM has built up two DC magnetron sputtering assemblies: a small tabletop setup for the production of samples sized 100mm x 100mm as well as a large plant – see Fig. 1 - for the fabrication of plates sized 700mm x 65mm. Both assemblies have successfully been operated in the past with surrogate materials as copper or stainless steel and the process of full size foil production as well as the process of cladding respectively depositing a barrier layer on these foils have been shown successfully [20]. 19 of 455
Page 2 and 3: © 2009 European Nuclear Society Ru
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Page 22 and 23: References [1] D. AB. Robinson et a
Page 24 and 25: • CNEA have been working in the f
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DECOMMISSIONING PROGRESS OF THE DOU
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SECURITY OF SUPPLY FOR FISSION MEDI
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But the worst crisis developed by e
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IRE and COVIDEN are following close
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Fig 1. Design of the core and refle
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Table 3: Set of detailed fuel funct
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For the thermal-mechanical analysis
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Behaviour under conditions represen
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6. References [1] - MC. Anselmet, G
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2. Advanced nuclear fuel cycles The
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3.3 India In addition to the ration
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Session II Fuel Development 90 of 4
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1. Introduction Since 1957, date of
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A 3.1. Place a boron insert in a hi
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Finally, a new tool was defined and
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the end user (CEA), to define the f
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Previous papers discussed character
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(a) (b) (c) (d) (e) (f) (g) (h) (i)
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The results of a third reported irr
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In order to reproduce the heat tran
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25 OXIDE THICKNESS 20 Kim et al pH=
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Heavy ion irradiation of UMo7/Al fu
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For the lowest flux values tested d
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127 I beam 127 I beam 0 5 10 15 20
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Weight fractions (%) U(α) UO 2 γU
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activities to meet the need. The co
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Heat capacity Information Thermal c
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Decision point Activity Phase 2: Fu
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IRIS PROGRAM: IRIS4 FIRST RESULTS F
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The main characteristics of the IRI
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4. In-pool plate thickness measurem
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At that stage of IRIS4 irradiation
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extrapolated thermal property value
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optical microscope, acoustic emissi
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CD WIRES AS BURNABLE POISON FOR THE
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Figure 1. MCNP geometry model of fu
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considered carefully: (i) maintain
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discussed and validated together, k
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The as-fabrication Si contents in t
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uniform Si diffusion and consequent
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Recently, fuel relocation induced b
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characteristics of ILs obtained in
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- Type 2 (Si content ≥ 5 wt%) : c
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4. Discussion The main contribution
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METHODS OF INCREASING THE URANIUM C
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• strength properties of Zr-1% Nb
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4. References 1. Birzhevoy G.A., Ka
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Dispersion fuel Monolithic fuel ATR
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− because of its Newtonian charac
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Session III Back-end 166 of 455
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Fig.1. The transfer hall (left in c
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The shipment included all the SNF f
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FRESH AND SPENT NUCLEAR FUEL REPATR
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modifications, spent fuel inspectio
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The shipment cleared Romanian Custo
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steel are chosen as effective gamma
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Fig 3. Long lived nuclides radioact
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Session IV Innovative Methods in Re
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Lower Gr-reflector Al-clad Upper Gr
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All described fuel elements were ca
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ANALYSIS OF NEW SAFETY CRITERIA FOR
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3.2 Strain limit The value of 3.65%
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The comparison between clad tempera
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VALIDATION OF PLTEMP/ANL V3.6 CODE
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ΔT p 0.0234 2 ⎪⎧ q[W/cm ] ⎪
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Table II. Hot Channel Factors for B
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for the U-8Mo fuel meat [5]. The po
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correlation of Dittus-Boelter; the
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ROLE OF RELAP/SCDAPSIM IN RESEARCH
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SEVERE REACTIVITY INJECTION ACCIDEN
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expansion and steam formation were
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3 Conclusion Since a few years, IRS
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analysis procedure (ENAA) except vi
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References Briesmeister, J.F., 2000
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Fig. 1 A geometric diagram of NIRR-
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Fuel plate temperatures during oper
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the primary circuit in the central
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Fig. 3: Surface temperature over th
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[4] “Test Irradiations of Full Si
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The core is made of 1488 stainless
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4. Commissioning the facility for t
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ESTABLISHMENT OF A SINGLE-CRYSTAL F
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were provided to MU and INL for thi
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concrete covered with sheets of 1.2
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USE OF FISSION RADIATION IN LIFE SC
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Fig. 3. Scan of an etch track film
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Summary The unique fission neutron
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2. Methods 2.1 Reactor produced rad
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3.2 Viability studies The results o
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DESIGN OF A FLOWING-NAK EXPERIMENTA
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4. Containment rig and sample-holde
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7. Electrical heater The external h
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Page 1 / 7 EVITA: a semi-open loop
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Page 3 / 7 Fig.1: EVITA fuel Genera
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Page 5 / 7 Challenges When operatin
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Page 7 / 7 References: [1] M.C. Ans
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Nuclear Research Institutes, and so
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According to the latest IAEA inform
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18. May Training of operating perso
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2.1 Irradiation Facilities Brief te
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3.1 Detection limits Although it is
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PARTIAL DISMANTLING OF RESEARCH REA
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• Core - liable to full scale rep
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• Necessary individual dosimetry
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SILICON DOPING AT FRM II H. GERSTEN
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The resulting neutron flux density
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4. References [1] Wagner F.M., Knes
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The choice of fuel base and solutio
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3.3 Increasing power beyond current
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A COATING TO PROTECT SPENT ALUMINIU
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The treatment consisted of simple i
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5. Conclusions 1. Immersion of AA 1
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KEEPING AGING RESEARCH REACTORS IN
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inspected in presence of an expert
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After the inspection was finished,
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1 A STRATEGY FOR MANAGING AGEING CO
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3 2. With the aluminium-clad HEU fu
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5 The pool and the support structur
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Fig.2. Reflector element of JRR-4.
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Dimensional change (%) 0.6 0.5 0.4
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SAFETY CONSIDERATIONS FOR CORE MANA
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3 3. Core operation and monitoring
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5 temperature, etc.). Effective sec
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1436 keV, Cs 138 1369 keV, Na 24 2.
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compared with that of the delayed n
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AD-HOC AND PREVENTATIVE MAINTENANCE
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Page 3 of 7 3. SAFARI-1OPERATIONAL
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Page 5 of 7 programs for instrument
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Page 7 of 7 DATE DESCRIPTION DATE D
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MICROSTRUCTURAL ANALYSIS OF MTR FUE
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In sample S3, similar zones could b
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increased temperature, the solid st
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Figure 8 BEI images covering Sample
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660 °C, but since in the former me
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support. Both Governments have eval
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• Removal of sludge from the SNF
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UPGRADED REACTOR SYSTEMS FOR ENHANC
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Parameter HEU LEU a 6.0x10 -5 (°K)
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From 1992 until 2005 the TRIGA-SSR
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Figure9 - Dependency between reacto
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URANIUM CONTAMINATION IN PRIMARY CI
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1.00E+06 1.00E+05 Volume activity (
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6. Acknowledgement This work was pe
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2. Steady State Thermal Hydraulic A
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in the scram, and the respective re
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CORROSION BEHAVIOR OF ALUMINIUM ALL
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3.2. Pitting corrosion of 1050 and
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4. Discussions This study shown tha
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The Steady State core was fully con
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0.E+00 2.E+06 1.40E+07 2.E+06 1.20E
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SYNTHESIS AND CHARACTERIZATION OF G
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0 2 4 6 8 10 120 1,2 100 1,0 80 70
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Element, Wt %, At %, K‐Ratio, Z,
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U/cc, but the target uranium densit
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Fig. 5 Macroscopic cutting view (x
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SELF-ASSESSMENT OF APPLICATION OF T
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2. The Code of Conduct on the Safet
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For emergency preparedness, conside
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inside of a compaction die by blowi
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Fig. 4. A compacted and sintered lu
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THE MANAGEMENT SYSTEM EVOLUTION OF
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etween CRPq specific process and IP
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aspect audits, mainly in relation t
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1 2 3 4 5 6 7 8 9 A B C D E F G H F
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MCNP5 is capable of calculating ter
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Similar to the case of stainless st
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LEU FUEL DISPOSITION AT WWR-M REACT
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Tested fuel assembles are load in t
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The PNPI experience of tests with W
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CURRENT UTILIZATION AND LONG TERM S
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Uusimaa hospital district decided t
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FiR 1 has an important regional rol
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STUDYING OF INFLUENCE OF A NEUTRON
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Definition of crystal structure and
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Microhardness measurement shows, th
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THE SPENT FUEL STORAGE AT THE DALAT
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2. Interim storage of spent fuel On
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A rotating bridge crane of 3.6-ton
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In order to investigate the perform
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(a) (b) Fig. 2. (a) low and (b) hig
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(a) (b) (c) (d) (e) (f) Fig. 5. TEM
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Spot Al Si Mo U Zr G 90.6 7.8 0.6 0
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volume in the material, which affec
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THE STEREOMETRIC ANALYSIS OF GAS PO
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of the crack of pillowing). It show
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One gets the impression that during
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switch from a fast to a thermal spe
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He production to fission ratio vs t
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INSPECTION EXPERIENCE WITH IEA-R1 S
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camera system, received from IAEA i
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core in the beginning 2007 (IEA-174
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RRFM 2009 Transactions - European Nuclear Society

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