RRFM 2009 Transactions - European Nuclear Society

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Parameter HEU LEU a 6.0x10 -5 (°K) -1 5.5x10 -5 (°K) -1 Keff 0.00725 0.00730 Tcmax 705 °C 617 °C Core life time 8000 MWD (29 fresh HEU fuel) 4500 MWD (11 fresh and 18 burned LEU fuel) Table2 Shim bundle removal Pmax 550 MW 500 MW T C max 810 °C 773 °C * Note: * Temperature for 29 LEU is lower than for 29 HEU due to PPF (29 LEU) =2.14, which is lower than PPF (29 HEU) = 2.5 Figure2 shows the dependency between Keff and MWD for the actual configuration with 29 LEU fuel bundles: 1,06 Figure2 – Dependency between Keff in MWD 1,05 1,04 Keff 1,03 1,02 1,01 1 0 1000 2000 3000 4000 5000 MWD The new reactivity control system consisting in 8 control rods assures reactor operation in comply with operational limits and conditions. The following figure illustrates the differencies between the B10 arrangement for old and new control rods: Figure3 – Geometrical differencies between the new and old control rod concepts 348 of 455
The worth difference between new and old control rods is shown in the following table and graphic: Table2 Worth difference between new and old control rods Control Worth ($) rod Old New Difference (%) 1. 305,3 283,7 7 2. 291,2 270,4 7,1 3. 547,3 523,4 4,4 4. 213,9 190, 11,2 5. 90,7 76,3 15,9 6. 91,7 93,2 - 7. 48,9 45,2 - 8. 26,4 23,8 10 CENTS Figure4 – Worth difference between old (red) and new (blue) control rod #3 540 520 500 480 460 440 420 400 380 360 340 320 300 280 260 240 220 200 180 160 140 120 100 80 60 40 20 0 100 150 200 250 300 350 400 450 500 550 600 650 700 750 800 850 900 UNITS The measured fuel temperature at full power (14MW) is a safety limit for TRIGA reactor. The comparative results are: Maximum temperature at 14MW in the most used LEU pin – burned fuel: - Central=617 0 C - Peripheral=226 0 C - Clad=114 0 C Maximum temperature at 14MW in the used LEU pin – fresh fuel: - Central=439 0 C - Peripheral=170 0 C - Clad=89 0 C 349 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 - 3 / 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
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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
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
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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
Page 342 and 343: support. Both Governments have eval
Page 344 and 345: • Removal of sludge from the SNF
Page 346 and 347: UPGRADED REACTOR SYSTEMS FOR ENHANC
Page 350 and 351: From 1992 until 2005 the TRIGA-SSR
Page 352 and 353: Figure9 - Dependency between reacto
Page 354 and 355: URANIUM CONTAMINATION IN PRIMARY CI
Page 356 and 357: 1.00E+06 1.00E+05 Volume activity (
Page 358 and 359: 6. Acknowledgement This work was pe
Page 360 and 361: 2. Steady State Thermal Hydraulic A
Page 362 and 363: in the scram, and the respective re
Page 364 and 365: CORROSION BEHAVIOR OF ALUMINIUM ALL
Page 366 and 367: 3.2. Pitting corrosion of 1050 and
Page 368 and 369: 4. Discussions This study shown tha
Page 370 and 371: The Steady State core was fully con
Page 372 and 373: 0.E+00 2.E+06 1.40E+07 2.E+06 1.20E
Page 374 and 375: SYNTHESIS AND CHARACTERIZATION OF G
Page 376 and 377: 0 2 4 6 8 10 120 1,2 100 1,0 80 70
Page 378 and 379: Element, Wt %, At %, K‐Ratio, Z,
Page 380 and 381: U/cc, but the target uranium densit
Page 382 and 383: Fig. 5 Macroscopic cutting view (x
Page 384 and 385: SELF-ASSESSMENT OF APPLICATION OF T
Page 386 and 387: 2. The Code of Conduct on the Safet
Page 388 and 389: For emergency preparedness, conside
Page 390 and 391: inside of a compaction die by blowi
Page 392 and 393: Fig. 4. A compacted and sintered lu
Page 394 and 395: THE MANAGEMENT SYSTEM EVOLUTION OF
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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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