RRFM 2009 Transactions - European Nuclear Society

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4. In-pool plate thickness measurements The plate thickness measurements were collected plate by plate, at each intercycle, on five axial and one transverse (at the MFP) profiles 3 (fig. 3a and 3b). Note that the measurements after the 2 nd cycle F230 are not available due to technical problems encountered on the inpool measurement device at that moment. The precision of these measurements is about 15 µm. As can be seen in Fig. 3a, the plate 8044 testing oxidised UMo in Al+2.1%Si did not show abnormal swelling after the fourth cycle (peak BU estimated to ~38%). The thickness of both plates containing oxide coated UMo + Si increased normally as irradiation proceeded. The maximal thickness increase for the hottest plate (8044) was between 40 and 50 µm at the end of cycle F232, taking into account thickness measurement differences between axial and transverse profiles performed at MFP (see Fig. 3a). By comparison, Fig. 3b shows the thickness evolution of plate 8053 containing oxidised UMo particles dispersed in pure Al. Fig.3b indicates a more heterogeneous swelling, particularly during the 4 th cycle. Local thickness increases up to 70 µm have been measured. Same results are evidenced for the plate 8054. IRIS4 plates without silicon added to the Al matrix show a slightly higher swelling than those with 2.1%Si. Plate 8044 (UMo ox - 2.1 wt% Si) Plate 8053 (UMo ox - 0% Si) before axial points - before F229 F231 F232 axial points - F232 1370 1360 before F229 F231 F232 1390 1380 1370 1350 1360 Plate thickness (μm) 1340 1330 1320 Plate thickness (μm) 1350 1340 1330 1310 1320 1300 1310 1290 1300 -30 -20 -10 0 10 20 30 transverse position (mm) Fig. 3a: In-pile evolution of the transverse thickness profiles of plate 8044 at MFP -30 -20 -10 0 10 20 30 transverse position (mm) Fig. 3b: In-pile evolution of the transverse thickness profiles of plate 8053 at MFP 5. Discussion IRIS4 experiment is currently testing for the first time the behaviour of oxidised UMo fuel dispersed in pure Al or in Al+2.1%Si alloy matrix using full-size plates. In order to discriminate both effects of oxide layer and silicon addition on the UMo irradiation behaviour, the average plate thickness versus the fission density is represented on Fig. 5, comparing results of IRIS2 (pure Al), IRIS3 (2.1%Si and 0.3%Al) and IRIS4. Fig. 4 reminds the heat flux history for these three IRIS experiments. At the current status of IRIS4 experiment, if we compare the behaviour of UMo fuel without Si, one can notice that no pillowing has occurred in IRIS4 plates whereas, at similar fission density and even lower temperature, large pillowing was already observed on IRIS2 plates (whose irradiation conditions were higher than IRIS3 ones). However, local thickness results from Fig. 3b could indicate a beginning of degradation of the oxidised UMo plates. 3 These measurements are done in the OSIRIS reactor pool with a dedicated device, originally developed for the qualification of the U 3 Si 2 fuel. 128 of 455
In that case, one can assume that oxidised UMo would hinder the interaction rate UMo/Al without really modifying its intrinsic characteristics. Behaviour of plates 8053 and 8054 during the further cycles will definitely confirm or not this assumption. The behaviour of the two others plates (8043 and 8044) testing the both contribution of the oxide layer and the Si addition is promising since the thickness increase of those plates is of the same order of magnitude as that of the IRIS3 plate 8021 containing Al+Si but irradiated at much lower heat flux (below 200 W/cm² against more than 285 W/cm² for the IRIS4 plates). Until now, positive effect of 2.1%Si addition in the Al matrix is confirmed in higher irradiation conditions. The potential contribution effect of oxidised UMo particle should be discriminate in the further irradiation cycles. Peak Heat Flux (W.cm-2) 350 300 250 200 150 100 50 0 Power history IRIS 2 (Pure Al) 2002 IRIS 3 (Al+2.1%Si) 8021 0 50 100 150 Duration (days) Fig.4: IRIS2, IRIS3 and IRIS4 power history comparison IRIS 4 (UMo ox +2,1%Si) 8044 Plate thickness increase (µm) 300 250 200 150 100 IRIS2 0%Si (U7MT2002) IRIS2 0%Si (U7MT2003) IRIS2 0%Si (U7MT2007) IRIS3 0,3%Si (U7MV8011) IRIS3 2,1%Si (U7MV8021) IRIS4 UMo ox - 2,1%Si (U7MZ8044) IRIS4 UMo ox - 2,1%Si (U7MZ8043) IRIS4 UMo ox - 0%Si (U7MZ8054) IRIS4 UMo ox - 0%Si (U7MZ8053) 371 µm 1237 µm 1056 µm pillowing IRIS2 0% Si P < 230 W/cm² IRIS2 0% Si P < 240 W/cm² IRIS3 0,3% Si P < 183 W/cm² 50 IRIS3 2,1% Si P < 201 W/cm² 0 0,00 0,50 1,00 1,50 2,00 2,50 3,00 3,50 4,00 4,50 6. Conclusion Fission density (10 21 f/cm 3 UMo) Fig. 5: Plate swelling of IRIS2, IRIS3 and IRIS4 plates IRIS4 consists in four full-size plates with high uranium loading and U-7.3 wt %Mo oxidised atomised powder dispersed in pure or added with silicon aluminium matrix. In this latest IRIS4 experiment still on-going, a modification of the UMo/Al interface is considered. The concept of protective barrier with the use of an oxide layer surrounding UMo particles was promoted by out-of-pile results [10, 11]. Up to now, the IRIS4 plates were irradiated during 58 EFPD at OSIRIS reactor at a peak power of more than 290 W.cm -2 . The first results show that in the tested conditions, i.e. fission density of about 2.5 10 21 f.cm -3 UMo, no pillowing occurred. For oxidised UMo fuel dispersed in pure Al, plate thicknesses have slightly more increased than for plates with Si added in Al. 129 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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Page 82 and 83: Behaviour under conditions represen
Page 84 and 85: 6. References [1] - MC. Anselmet, G
Page 86 and 87: 2. Advanced nuclear fuel cycles The
Page 88 and 89: 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
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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 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 140 and 141: considered carefully: (i) maintain
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
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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
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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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