RRFM 2009 Transactions - European Nuclear Society

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• CNEA have been working in the fabrication of depleted 8 gU/cm 3 U-7Mo based miniplates. Once this process is stable and repetitive, the fabrication of a LEU prototypic fuel assembly will follow. • In order to avoid an undesirable porosity in the aluminium side of the interaction zone with U-Mo due to the migration of gas fission products, and according to studies done on the convenience to add a proper component to matrix powder, Al-Si alloys were employed. Fabrication conditions of dispersed U-Mo miniplates and scalingup to plate size related problems were achieved. • Concerning very high density monolithic U-Mo both miniplates and plates, using MEU and LEU fuel meat with Zry-4 cladding to be irradiated in USDoE-ATR Reactor, are being developed • In order to improve material performance and plate dimensioning fabrication conditions were studied and modified, like hot co-lamination of U-Mo and Zry-4 sheaths. Several depleted uranium prototypes were elaborated, characterized and tested to set up process variables and fabrication conditions. 4. Improvement of the LEU target and radiochemical technology for Mo99 and other radioisotopes production: It was already presented that CNEA has decided on 2001 to turn into LEU material for target fabrication, maintaining other characteristics of the production, i.e. the alkaline chemical digestion process. CNEA has been producing Mo-99 using LEU since 2002.CNEA produces Mo-99 primarily for its domestic market and secondarily for export to other South American countries. It began producing Mo-99 using HEU targets in 1985[i] and developed and converted to LEU-based production in 2002. CNEA manufactures its own uranium-aluminum alloy plate LEU targets[ii]. • CNEA has developed and is using high-density LEU-aluminum dispersion targets to produce Mo-99 for its domestic market. The target meat has a density of 2.9 gU/cm3, which is obtained by increasing the ratio of uranium aluminide to aluminum in the target meat. The mass of U-235 in the target meat is about twice that of conventional uranium-aluminum alloy targets. • CNEA was able to convert to LEU-based production in the same set of hot cells that were being used for HEU-based production. Moreover, this conversion was made without interrupting Mo-99 production • Targets are irradiated in the RA-3 reactor at CNEA’s Ezeiza Atomic Center near Buenos Aires. Target processing is carried out in a hot cell facility at the Ezeiza site. Process wastes are also managed at the site. • CNEA’s development showed that there are no technical barriers to conversion of Mo-99 production from HEU targets to LEU targets. Production using LEU targets is technically feasible and is being carried out by CNEA in Argentina and will be shortly by the Australian National <strong>Nuclear</strong> Science and Technology Organisation (ANSTO) using CNEA technology using CNEA-developed LEU targets and target dissolution process to produce Mo-99. • This new LEU technology satisfies the most stringent requirements of quality for its use in nuclear medicine applications. Mo-99 purity has been consistently higher than that produced using HEU targets[iii] • Also in September 2005, CNEA began the regular production of high quality fission I-131, a by-product of Mo-99 production, meeting also international quality standards. • New results are that HEU-LEU production process comparison costs reveals that this new technology has no significant over cost. CNEA recently presented a comparison of its variable costs for producing Mo-99 using LEU and HEU targets[iv]. Variable costs for Mo-99 production for the three years prior to (i.e., 1998-2001) and three years following (2003-2007) conversion were compared. Costs were presented in three categories: (1) labor; (2) materials; and (3) services, maintenance, taxes, and miscellaneous. The costs were presented as present value estimates normalized on a per curie basis for the number of curies produced 24 of 455
in 2007. Overall costs for LEU-based production compared to HEU-based production increased by about 5 percent. • Conclusions: no technical, quality or financial reasons make disadvantageous to change from HEU to LEU radiochemical technology for Mo99 and other radioisotopes production. CNEA becomes a leader in LEU based isotope production technology, and with INVAP built all-LEU production systems in Australia and Egypt • Future plans: at present, CNEA is considering to expand Mo-99 production within its current facilities by increasing target throughputs. Such an expansion would put CNEA in the ranks of large-scale producers . 5. Conclusions: CNEA continues deploying development activities on LEU technology for core reactor conversion and Mo99 and related radioisotope production. Future plans include prototypic fuel irradiation and optimization of LEU targets and alkaline digestion process. i Cols, H. J., P. R. Cristini, and A. C. Manzini. 2000. Mo-99 from low-enriched uranium. 2000 International RERTR Meeting, Las Vegas, Nevada, USA, 1-6 October, 2000. Available at http://www.rertr.anl.gov/Web2000/PDF/Cristi00.pdf ii Kohut, C., M. de la Fuente, P. Echenique, D. Podesta, and P. Adelfang. 2000. Target development of low enrichment for production of 99Mo for fission. 2000 International RERTR Meeting, Las Vegas, Nevada, USA, 1-6 October, 2000. Available at http://www.rertr.anl.gov/Web2000/PDF/Fuente00.pdf iii Durán,A. 2005. Radionuclide Purity of Fission Mo-99 Produced from LEU And HEU. A Comparative Study. 2005 International RERTR Meeting, Boston, Massachusetts, USA, November 6-10, 2005. Available at http://www.rertr.anl.gov/RERTR27/PDF/S8- 3_Duran.pdf. iv Cestau D., A. Novello, P. Cristini, M. Bronca, R. Centurión, R. Bavaro, J. Cestau, E. Carranza. HEU and LEU cost comparison in the production of molybdenum-99. 2008 International RERTR Meeting, Washington, DC, USA, 5-9 October 2008, and Cestau D., A. Novello, P. Cristini, M. Bronca, R. Centurión, R. Bavaro, J. Cestau, E.Carranza. 2007. HEU and LEU comparison in the production of molybdenum-99. 2007 International RERTR Meeting, Prague, Czech Republic, Sep. 23-27, 2007. Available at http://www.rertr.anl.gov/RERTR29/PDF/6-4_Cestau.pdf 25 of 455
Page 2 and 3: © 2009 European Nuclear Society Ru
Page 4 and 5: RESEARCH REACTOR COALITIONS - SECON
Page 6 and 7: - Eastern European Research Reactor
Page 8 and 9: ut a comprehensive alignment of tec
Page 10 and 11: EERRI will be launched. As noted ab
Page 12 and 13: Nuclear material in the form of hig
Page 14 and 15: The GTRI domestic radiological mate
Page 16 and 17: 2. State of the art For fuel plate
Page 18 and 19: It is known since the early days of
Page 20 and 21: End of 2008 first DU-8wt.%Mo (deple
Page 22 and 23: References [1] D. AB. Robinson et a
Page 26 and 27: O 75 Bignan.doc - DI - 1 / 10 20/02
Page 36 and 37: THE EAST EUROPEAN RESEARCH REACTOR
Page 38 and 39: namely Jozef Stefan Institute TRIGA
Page 40 and 41: Information and organizational issu
Page 42 and 43: Action Item Table 3. Description (t
Page 44 and 45: Table 6. Materials/fuel test experi
Page 46 and 47: In a recent development, it should
Page 48 and 49: 1. Introduction: a renewed context
Page 50 and 51: interaction, close retention of fis
Page 52 and 53: 3.3 Reference concept and alternati
Page 54 and 55: changes can be caused by void swell
Page 56 and 57: For its manufacturing, an additiona
Page 58 and 59: minor actinides (MA) considered as
Page 60 and 61: In France, the decision to build a
Page 62 and 63: eactors (HFR, OSIRIS and then JHR)
Page 64 and 65: DECOMMISSIONING PROGRESS OF THE DOU
Page 70 and 71: SECURITY OF SUPPLY FOR FISSION MEDI
Page 72 and 73: 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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