RRFM 2009 Transactions - European Nuclear Society

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Definition of crystal structure and parameter of lattice of alloys was spent on X-ray diffractometer DRON-3М (l =0,15418 nanometers). According to the radiographic analysis, as expected, initial alloys SAV-1 and AMG-2 have face-centered cubic arrangement with lattice parameter, a = 4,066 ± 0,003 Å and a = 4,0726±0,003 Å, accordingly. Small increase of alloys’ lattice parameter in comparison with the reference aluminum sample (4,0414 Å) is result of the presence of impurity in them. To determine the elemental composition and structure of the samples, the latter were studied with the help of the micro analyzer “Jeol” JSM 5910 IV- Japan. Tables 4 and 5 summarize contents (%) of the elements Mg, Al, Fe, Si и Cu for the alloys SAV-1 and AMG-2, correspondingly, before and after the samples were subjected to 10 19 n/cm 2 fluencies. It is worth noting that data in table 4 coincides with published data for the SAV-1 and AMG-2 samples. In addition, the tables contain the measurement data only for those points which fail to appear in the area of local formations of insoluble intermetal phases. Tables 4 and 5 present screened illustration of the samples SAV-1 for elements Mg, Al, Fe и Si before and after irradiation with the fluence of 10 19 n/cm 2 , correspondingly. Fig. 2 shows local formations by way of white stains of insoluble inter-metal phases of Al-Mg-Si-Fe type with the size of 1 - ≥10 μm (for example, see Fig. 2 for Si). The measurement of the element content at these two points has given the following result: Point I: Al − 66,72%; Mg − 11,06%; Si − 15,80%; Fe −5,96%. Point II: Al − 69,70%; Mg − 4,88%; Si − 13,37%; Fe −11, 63%. It is seen in Fig.3 that after being irradiated, the surface of the sample is oxidized and the local insoluble intermetal phases of the Al-Mg-Si-Fe type are broken up and scattered over a large volume of the sample becoming actually evenly distributed over all the volume. It is especially well-seen on the pictures (Fig. 3) of the elements Fe and Mg. Such a breaking up of the local insoluble intermetal phases in the final analysis has caused a considerable change in the elemental composition in the three points measured which is seen in Table 5. It seems that a considerable change in the size of the local insoluble intermetal phases causes a change in the thermal conductivity, specific resistance, as well as microhardness of the samples when the latter have been subjected to irradiation. The further investigations will be devoted to determination of the above-mentioned characteristics of the samples. Sample Analysis # Mg Аl Si Mn Fe Сu Total SAV-1 1 1,00 98,42 0,45 0,00 0,14 0,00 100,00 SAV-1 2 1,04 98,24 0,54 0,00 0,13 0,06 100,00 SAV-1 3 1,15 98,12 0,51 0,02 0,14 0,06 100,00 Average 1,06 98,26 0,50 0,01 0,14 0,04 100,00 AMG-2 4 2,81 96,72 0,00 0,21 0,27 0,00 100,00 AMG-2 5 2,77 96,65 0,00 0,27 0,25 0,07 100,00 AMG-2 6 2,82 96,72 0,00 0,24 0,23 0,00 100,00 Average 2,80 96,70 0,00 0,24 0,25 0,02 100,00 Table 4. Elemental composition of the main admixtures (%) in the SAV-1 and AMG-2 samples before being irradiated with a neutron flux Sample Analysis # Mg Аl Si Fe Сu Total SAV-1 1 0,48 96,33 2,72 0,44 0,04 100,00 SAV-1 2 0,57 97,42 1,77 0,25 0,00 100,00 SAV-1 3 0,55 97,054 1,66 0,27 0,00 100,00 Average 0,53 97,09 2,05 0,32 0,01 100,00 AMG-2 4 1,230,57 97,51 0,58 0,68 0,00 100,00 AMG-2 5 1,56 97,204 0,56 0,68 0,00 100,00 AMG-2 6 1,71 97,32 0,57 0,31 0,09 100,00 Average 1,50 97,34 0,57 0,56 0,03 100,00 Table 5. Elemental composition of the main admixtures (%) in the SAV-1 and AMG-2 samples after being irradiated with the fluence of 10 19 n/cm 2 420 of 455 3
Fig. 2. Microstructure of SAV-1 initial alloy (before irradiation) Fig. 3. Microstructure of SAV-1 alloy after irradiation with 10 19 n/cm 2 fluence 421 of 455 4
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© 2009 European Nuclear Society Ru
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RESEARCH REACTOR COALITIONS - SECON
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- Eastern European Research Reactor
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ut a comprehensive alignment of tec
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EERRI will be launched. As noted ab
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Nuclear material in the form of hig
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The GTRI domestic radiological mate
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2. State of the art For fuel plate
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It is known since the early days of
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End of 2008 first DU-8wt.%Mo (deple
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References [1] D. AB. Robinson et a
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• CNEA have been working in the f
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O 75 Bignan.doc - DI - 1 / 10 20/02
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O 75 Bignan.doc - DI - 9 / 10 20/02
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THE EAST EUROPEAN RESEARCH REACTOR
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namely Jozef Stefan Institute TRIGA
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Information and organizational issu
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Action Item Table 3. Description (t
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Table 6. Materials/fuel test experi
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In a recent development, it should
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1. Introduction: a renewed context
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interaction, close retention of fis
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3.3 Reference concept and alternati
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changes can be caused by void swell
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For its manufacturing, an additiona
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minor actinides (MA) considered as
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In France, the decision to build a
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eactors (HFR, OSIRIS and then JHR)
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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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Page 374 and 375: SYNTHESIS AND CHARACTERIZATION OF G
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Page 378 and 379: Element, Wt %, At %, K‐Ratio, Z,
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Page 382 and 383: Fig. 5 Macroscopic cutting view (x
Page 384 and 385: SELF-ASSESSMENT OF APPLICATION OF T
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Page 396 and 397: etween CRPq specific process and IP
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Page 406 and 407: LEU FUEL DISPOSITION AT WWR-M REACT
Page 408 and 409: Tested fuel assembles are load in t
Page 410 and 411: The PNPI experience of tests with W
Page 412 and 413: CURRENT UTILIZATION AND LONG TERM S
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Page 418 and 419: STUDYING OF INFLUENCE OF A NEUTRON
Page 422 and 423: Microhardness measurement shows, th
Page 424 and 425: THE SPENT FUEL STORAGE AT THE DALAT
Page 426 and 427: 2. Interim storage of spent fuel On
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Page 430 and 431: In order to investigate the perform
Page 432 and 433: (a) (b) Fig. 2. (a) low and (b) hig
Page 434 and 435: (a) (b) (c) (d) (e) (f) Fig. 5. TEM
Page 436 and 437: Spot Al Si Mo U Zr G 90.6 7.8 0.6 0
Page 438 and 439: volume in the material, which affec
Page 440 and 441: THE STEREOMETRIC ANALYSIS OF GAS PO
Page 442 and 443: of the crack of pillowing). It show
Page 444 and 445: One gets the impression that during
Page 446 and 447: switch from a fast to a thermal spe
Page 448 and 449: He production to fission ratio vs t
Page 450 and 451: INSPECTION EXPERIENCE WITH IEA-R1 S
Page 452 and 453: camera system, received from IAEA i
Page 454: core in the beginning 2007 (IEA-174
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