RRFM 2009 Transactions - European Nuclear Society

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The treatment consisted of simple immersion of the specimens in the solutions. Solution-1 was used to pickle and remove the surface oxide. Solutions 2 and 3 were used to form the coating. After treatment, the specimens were rinsed and their surfaces examined. Untreated and treated specimens were exposed to 0.001 M and 0.1 M NaCl solutions for 1 and 4 hours to determine their corrosion resistance. The surfaces of specimens: (a) untreated; (b) after treatment in the Ce containing solutions; (c) after exposure to NaCl solutions were examined in a scanning electron microscope (SEM) coupled to an energy dispersive spectrometer (EDS). The electrochemical behavior of untreated and treated specimens of the two alloys was determined from anodic potentiodynamic polarization measurements carried out with an electrochemical system using a standard 3-electrode arrangement in 0.1 M NaCl. 3. Results and discussion The surfaces of AA 1100 and AA 6061 specimens immersed in Solution-2 revealed non-uniformly distributed CeO 2 on the former and preferred formation of CeO 2 at intermetallic precipitates (IMP) on AA 6061, as shown in Fig. 1a and in the EDS spectrum in Fig.1b. The AA 1100 and 6061 specimens immersed in Solution-3 Figure 1. (a) Scanning electron micrograph of AA 6061 surface treated in Solution-2. (b) EDS spectrum of surface at region 3 in Fig. 1a. Figure 2. (a) Scanning electron micrograph of AA 6061 surface treated in Solution-3. (b) EDS spectrum of surface at region 2 in Fig. 2a. revealed CeO 2 on the deposited Cu islands. CeO 2 was also observed on IMP in AA 6061. Other regions of the surface also revealed CeO 2 , but to a lesser extent as shown in Fig. 2. The EDS at region 2 in Fig.2a is shown in Fig.2b, revealing Cu and 294 of 455
Ce peaks. The Cu and IMP free regions revealed significantly less CeO 2 , due probably to the Al oxide on the surface. Specimens that were treated first in Solution- 1, to remove surface oxide followed by treatments in Solutions 2 or 3 revealed CeO 2 even at regions without Cu or IMP. The micrographs of CeO 2 coated AA 1100 and AA 6061 specimens did not reveal any marked changes upon exposure to NaCl of either concentration and for the two different durations. The results of the electrochemical measurements are summarized in table 3. The cerium dioxide coated specimens had higher corrosion potentials and lower corrosion currents. Specimens coated with CeO 2 from Solution-3 were even more corrosion resistant compared to those coated in solution-2. Increase in immersion time in either solution had no significant effect on the potential or the corrosion current. Overall, these data indicate that cerium dioxide conversion coatings on AA 1100 and AA 6061 clad spent RR fuel assemblies would significantly improve the pitting corrosion resistance of the assemblies in spent fuel basins with significantly lower quality water than that in use presently. Table 3. Corrosion current (I corr ) and potential (E corr ) of the alloys in 0.1M NaCl Alloy Treatment I corr ( mA.cm -2 ) E corr ( mV vs SCE) None 5 x 10 -6 - 850 AA 1100 Solution - 2 2 x 10 -6 - 730 Solution - 3 5 x 10 -7 - 660 None 4 x 10 -5 - 770 A 6061 Solution - 2 4 x 10 -6 - 790 Solution - 3 1 x 10 -6 - 630 4. The ARCAL project A Latin American project titled “Development of novel cost effective conversion coatings for long term safe wet storage of spent aluminium-clad research reactor fuels” has been approved for execution during <strong>2009</strong>-2012 and awaiting funding. The participating countries are Argentina, Brazil, Chile and Peru. The different stages of the project include: (a) development of transition metal (TM) and/or lanthanide conversion coatings on Al alloys; (b) evaluation of corrosion resistance of conversion coated mock fuel plates in Latin American spent fuel basins; (c) design and construction of a rig and remote handling equipment to conversion coat spent fuel assemblies; (e) Definition of procedures to prepare conversion coatings on spent fuel assemblies. 295 of 455
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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
Page 244 and 245: Fig. 3. Scan of an etch track film
Page 246 and 247: Summary The unique fission neutron
Page 248 and 249: 2. Methods 2.1 Reactor produced rad
Page 250 and 251: 3.2 Viability studies The results o
Page 252 and 253: DESIGN OF A FLOWING-NAK EXPERIMENTA
Page 254 and 255: 4. Containment rig and sample-holde
Page 256 and 257: 7. Electrical heater The external h
Page 258 and 259: Page 1 / 7 EVITA: a semi-open loop
Page 260 and 261: Page 3 / 7 Fig.1: EVITA fuel Genera
Page 262 and 263: Page 5 / 7 Challenges When operatin
Page 264 and 265: Page 7 / 7 References: [1] M.C. Ans
Page 266 and 267: Nuclear Research Institutes, and so
Page 268 and 269: According to the latest IAEA inform
Page 270 and 271: 18. May Training of operating perso
Page 272 and 273: 2.1 Irradiation Facilities Brief te
Page 274 and 275: 3.1 Detection limits Although it is
Page 276 and 277: PARTIAL DISMANTLING OF RESEARCH REA
Page 278 and 279: • Core - liable to full scale rep
Page 280 and 281: • Necessary individual dosimetry
Page 282 and 283: SILICON DOPING AT FRM II H. GERSTEN
Page 284 and 285: The resulting neutron flux density
Page 286 and 287: 4. References [1] Wagner F.M., Knes
Page 288 and 289: The choice of fuel base and solutio
Page 290 and 291: 3.3 Increasing power beyond current
Page 292 and 293: A COATING TO PROTECT SPENT ALUMINIU
Page 296 and 297: 5. Conclusions 1. Immersion of AA 1
Page 298 and 299: KEEPING AGING RESEARCH REACTORS IN
Page 300 and 301: inspected in presence of an expert
Page 302 and 303: After the inspection was finished,
Page 304 and 305: 1 A STRATEGY FOR MANAGING AGEING CO
Page 306 and 307: 3 2. With the aluminium-clad HEU fu
Page 308 and 309: 5 The pool and the support structur
Page 310 and 311: Fig.2. Reflector element of JRR-4.
Page 312 and 313: Dimensional change (%) 0.6 0.5 0.4
Page 314 and 315: SAFETY CONSIDERATIONS FOR CORE MANA
Page 316 and 317: 3 3. Core operation and monitoring
Page 318 and 319: 5 temperature, etc.). Effective sec
Page 320 and 321: 1436 keV, Cs 138 1369 keV, Na 24 2.
Page 322 and 323: compared with that of the delayed n
Page 324 and 325: AD-HOC AND PREVENTATIVE MAINTENANCE
Page 326 and 327: Page 3 of 7 3. SAFARI-1OPERATIONAL
Page 328 and 329: Page 5 of 7 programs for instrument
Page 330 and 331: Page 7 of 7 DATE DESCRIPTION DATE D
Page 332 and 333: MICROSTRUCTURAL ANALYSIS OF MTR FUE
Page 334 and 335: In sample S3, similar zones could b
Page 336 and 337: increased temperature, the solid st
Page 338 and 339: Figure 8 BEI images covering Sample
Page 340 and 341: 660 °C, but since in the former me
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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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