RRFM 2009 Transactions - European Nuclear Society

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considered carefully: (i) maintain the geometry of the fuel core, of the plates and of the fuel element in order to ensure the same thermo-hydraulic characteristics, (ii) ensure the swaging criteria, (iV) keep the stiffeners mechanical characteristics and (iiii) keep the current assembling process. As a part of the project, the manufacturing costs and delivery schedule of 2 BR2 fuel elements at Mol by Mid 2010 were took into consideration. 4.1 Mechanical calculations and proposed technical solution The stiffener geometry, principally the thickness, has to be modified in order to maintain the mechanical characteristics as well as ensure a perfect insertion of cadmium wires (see figure 3). The Cd wire dimension was selected by BR2. The design modification may avoid any major change on the fuel plate design. Figure 3: Fuel section with sheathed cadmium wires The new stiffener design and the stiffener mechanical characteristics were defined and validated by a series of specific mechanical tests. According to our experience on swaging, a technical investigation has shown that the mechanical modifications do not change the swaging parameters that were already qualified for BR2. As a consequence of the stiffener width modification, an analysis of the fuel plate geometry was performed in order to confirm their correct adaptation to the new design. Regarding the conventional criteria, some margin was found on plate and fuel dimension to successfully perform the modification without cost (processing modification…) and safety impact (thermo-hydraulic cooling aspect on the border edge in between the stiffener and the fuel area…). Taking into account our quality approach, the margin was validated throughout a full measurement campaign on existing plates. Thus, for the new fuel elements design, the border edge aluminium area (AA) and the stiffener groove edge (D), will remain the same as in the current BR2 fuel element (see figure 4). Most of all, the fuel element geometry will not be modified avoiding any long and costly safety demonstration and qualification program. As one of the most critical manufacturing step, a global approach was carried out to validate the swaging processing phase. AA *AREVA-CERCA, a subsidiary of AREVA NP, an AREVA an SIEMENS company 140 of 455
Figure 4: sketch of the future stiffener design The whole program was performed using the conventional mechanical tool design as CAD (Computer Assisted Design) allowing AREVA-CERCA to share and easily discuss the proposed solution with BR2 (Fig 5). Figure 5: Views of BR2 fuel element with sheathed cadmium wires 5. Conclusion In the framework of the ‘BR2 conversion project’, SCK●CEN and AREVA-CERCA are working closely for the design and manufacturing feasibility of new fuel elements. One important challenge is to deal with the replacement of the burnable poisons mixed in the fuel cores by cadmium wires inserted in the stiffeners. Technical options and solutions were *AREVA-CERCA, a subsidiary of AREVA NP, an AREVA an SIEMENS company 141 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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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
Page 90 and 91: Session II Fuel Development 90 of 4
Page 92 and 93: 1. Introduction Since 1957, date of
Page 94 and 95: A 3.1. Place a boron insert in a hi
Page 96 and 97: Finally, a new tool was defined and
Page 98 and 99: the end user (CEA), to define the f
Page 100 and 101: Previous papers discussed character
Page 102 and 103: (a) (b) (c) (d) (e) (f) (g) (h) (i)
Page 104 and 105: The results of a third reported irr
Page 106 and 107: In order to reproduce the heat tran
Page 108 and 109: 25 OXIDE THICKNESS 20 Kim et al pH=
Page 110 and 111: Heavy ion irradiation of UMo7/Al fu
Page 112 and 113: For the lowest flux values tested d
Page 114 and 115: 127 I beam 127 I beam 0 5 10 15 20
Page 116 and 117: Weight fractions (%) U(α) UO 2 γU
Page 118 and 119: activities to meet the need. The co
Page 120 and 121: Heat capacity Information Thermal c
Page 122 and 123: Decision point Activity Phase 2: Fu
Page 124 and 125: IRIS PROGRAM: IRIS4 FIRST RESULTS F
Page 126 and 127: The main characteristics of the IRI
Page 128 and 129: 4. In-pool plate thickness measurem
Page 130 and 131: At that stage of IRIS4 irradiation
Page 132 and 133: extrapolated thermal property value
Page 134 and 135: optical microscope, acoustic emissi
Page 136 and 137: CD WIRES AS BURNABLE POISON FOR THE
Page 138 and 139: Figure 1. MCNP geometry model of fu
Page 142 and 143: discussed and validated together, k
Page 144 and 145: The as-fabrication Si contents in t
Page 146 and 147: uniform Si diffusion and consequent
Page 148 and 149: Recently, fuel relocation induced b
Page 150 and 151: characteristics of ILs obtained in
Page 152 and 153: - Type 2 (Si content ≥ 5 wt%) : c
Page 154 and 155: 4. Discussion The main contribution
Page 156 and 157: METHODS OF INCREASING THE URANIUM C
Page 158 and 159: • strength properties of Zr-1% Nb
Page 160 and 161: 4. References 1. Birzhevoy G.A., Ka
Page 162 and 163: Dispersion fuel Monolithic fuel ATR
Page 164 and 165: − because of its Newtonian charac
Page 166 and 167: Session III Back-end 166 of 455
Page 168 and 169: Fig.1. The transfer hall (left in c
Page 170 and 171: The shipment included all the SNF f
Page 172 and 173: FRESH AND SPENT NUCLEAR FUEL REPATR
Page 174 and 175: modifications, spent fuel inspectio
Page 176 and 177: The shipment cleared Romanian Custo
Page 178 and 179: steel are chosen as effective gamma
Page 180 and 181: Fig 3. Long lived nuclides radioact
Page 182 and 183: Session IV Innovative Methods in Re
Page 184 and 185: Lower Gr-reflector Al-clad Upper Gr
Page 186 and 187: All described fuel elements were ca
Page 188 and 189: 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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