RRFM 2009 Transactions - European Nuclear Society

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ROLE OF RELAP/SCDAPSIM IN RESEARCH REACTOR SAFETY - RRFM 2009 is the University of Missouri Research Reactor located in the United States [9]. The SAFARI- 1 research reactor is a tank-in-pool type reactor operated at a nominal core power of 20MW. The core is cooled and moderated by forced circulation of light water. The reactor core can be operated in a variety of configurations from 24 to 32 fuel assemblies. Figure 1 shows an example of one such configuration. The fuel is U-Si-Al plate-type fuel elements. MURR is a 10 MW pool type reactor design with a pressurized primary coolant loop to cool the fuel region. The pressurized primary system is located in a pool allowing direct heat transfer during normal operation and transition to natural convection under accident conditions. The reflector region, control blade region, and center test hole are cooled by pool water (natural convection). Figure 1: SAFARI-1 Reactor Core Configuration. Because of the unique reactor designs, the RELAP/SCDAPSIM input models were developed separately by each organization and include a range of different nodalizations as presented in the reference papers. However in general terms, the RELAP/SCDAPSIM input models include all of the major components of each reactor system including the reactor tank, the reactor core and associated structures, and the reactor cooling system including pumps, valves, and heat exchangers. The secondary sides of the heat exchanger(s) are also modelled where appropriate. These input models were qualified through comparison with reactor steady state data, with original vendor safety analysis calculations where available, and with experiments in a limited number of cases. Figure 2 shows the nodalization used for the SAFARI-1 research reactor. The figure shows the overall system hydrodynamic nodalization with the upper right corner of the figure showing the core nodalization. Note from the insert of the core nodalization diagram that the bypass or unheated channels were modelled separately from the heated fuel assembly channels. The core nodalization also included two separate hot plate channels located on each side of the hottest plate. 206 of 455 3
ROLE OF RELAP/SCDAPSIM IN RESEARCH REACTOR SAFETY - RRFM 2009 Figure 2: RELAP/SCDAPSIM Nodalization of the SAFARI-1 Cooling System. A wide variety of transients have been analyzed using the code. Examples are included in the references and include reactivity initiated power excursions and loss of flow or coolant transients. RELAP/SCDAPSIM/MOD3.4 is used as the simulation engine for the SAFSIM PC based training simulator for SAFARI-1. The simulator is used as a training tool for reactor operators. The main purposes of the simulator is to 1) build operator experience, 2) provide operator training at all levels, 3) be a pre-examination for licensed operators, 4) train personnel in the setup of operating modes, 5) develop operating and emergency procedures, 6) analyze operating incidents and occurrences and 7) give the operator a general understanding of reactor behaviour under all sorts of fault and accident conditions. Figure 3 shows the simulator running on a typical PC with dual monitors. Figures 4a and 4b show more detailed pictures of portions of the control panel mimic. As shown by comparison to photographs of the SAFARI-2 control room panel, figures 5a and 5b, the SAFSIM represents the main features of the control room control panel and provides a visually realistic image for training purposes. At startup SAFSIM displays the reactor control room with the reactor completely shut down and the power supply to the protection mimic switched off. Therefore it is necessary for the trainee to go through the startup of all systems before the reactor can be started. The simulator was designed to give a realistic representation of the reactor and includes a very detailed representation of the reactor’s control system using a combination of standard RELAP5 control systems and reactor-specific coded algorithms which are linked to RELAP5 for the simulator. As a result, new operator training or operator retraining, which originally required the actual startup and operation of the reactor, can now be done on the simulator. The simulator also has an instructor’s panel from which the instructor can give the operator in training operational problems and challenges during a simulator session. Figure 6 shows the instructor’s panel display. 207 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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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
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
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
Page 190 and 191: 3.2 Strain limit The value of 3.65%
Page 192 and 193: The comparison between clad tempera
Page 194 and 195: VALIDATION OF PLTEMP/ANL V3.6 CODE
Page 196 and 197: ΔT p 0.0234 2 ⎪⎧ q[W/cm ] ⎪
Page 198 and 199: Table II. Hot Channel Factors for B
Page 200 and 201: for the U-8Mo fuel meat [5]. The po
Page 202 and 203: correlation of Dittus-Boelter; the
Page 204 and 205: ROLE OF RELAP/SCDAPSIM IN RESEARCH
Page 212 and 213: SEVERE REACTIVITY INJECTION ACCIDEN
Page 214 and 215: expansion and steam formation were
Page 216 and 217: 3 Conclusion Since a few years, IRS
Page 218 and 219: analysis procedure (ENAA) except vi
Page 220 and 221: References Briesmeister, J.F., 2000
Page 222 and 223: Fig. 1 A geometric diagram of NIRR-
Page 224 and 225: Fuel plate temperatures during oper
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Page 228 and 229: Fig. 3: Surface temperature over th
Page 230 and 231: [4] “Test Irradiations of Full Si
Page 232 and 233: The core is made of 1488 stainless
Page 234 and 235: 4. Commissioning the facility for t
Page 236 and 237: ESTABLISHMENT OF A SINGLE-CRYSTAL F
Page 238 and 239: were provided to MU and INL for thi
Page 240 and 241: concrete covered with sheets of 1.2
Page 242 and 243: 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
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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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