RRFM 2009 Transactions - European Nuclear Society

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• Necessary individual dosimetry control for the personnel ; • Monitoring for radioactive contamination; control over the radiation situation in the premises and radiation control of the air and the existing ventilation filters and supplementary (local) ventilation systems; • Monitoring of emissions; control over radioactive wastes and drainage waters, including in possible mobile facilities for low and middle active liquid RAW treatment; • Control over collection, sorting and categorization, storage and transportation of liquid and solid RAW. • The limit for the personnel effective dose is 100 mSv during 5 years, and the maximum effective dose for each year must not exceed 50 mSv according to [6]; • For the purposes of the radiation protection and in accordance with the ALARA principle, dose administrative limits are introduced for the personnel in IRT-Sofia. During the implementation of the partial dismantling the following working zones are defined in general: working zone admissible time for expected collective the stay in the zone, h dose On the premises of the 1-st circuit loop 72 4E-04 manSv At the reactor site (the reactot pool is full) 70 6E-05 manSv In the reactor pool (drained) 100 6E-03 manSv In the dismantling of the thermal column 165 4E-06 manSv externally On the site for secondary treatment and 82 10E-05 manSv decontamination of the dismantled equipment Site for carrying out measurements of the obtained materials 50 1E-06 manSv Fig. 4 Working zones In accordance with the ALARA principle the minimization of the dose exposure of the personnel is realized through: • Ventilation of workplaces - IRT-Sofia reactor is supplied with a standard ventilation system. For the needs of the partial dismantling it is accepted that its functions are going to provide some radiation protection of the workers. In the activities related to expected large amount of powder release (breaking of concrete, graphite blocks, cutting, etc.) a supplementary local ventilation system is also used, supplied with filters for dust removal; • Automation and mechanization of processes - the dismantling activities in the reactor pool are going to be carried out mechanically and remotely; • Radiation control systems - during the activities connected with the IRT-Sofia partial dismantling the radiation control system will continue to provide the necessary individual dosimetry control and control of radiation situation in the premises and radiation control of the air and the filters of working and supplementary (local) ventilation systems envisaged in the plan for partial dismantling; control of radioactive wastes and drainage waters; control over collecting, sorting and categorization, storage and transportation of liquid and solid RAW; • Using of individual protective means (clothing, breathing masks, etc.). On the basis of the prepared documents Detailed Plan for partial dismantling of IRT- Sofia equipment and Safety Analysis Report for the Partial Dismantling and with the assistance of US DOE and IAEA we proceed towards the implementation of the partial dismantling activities shortly. 280 of 455 5
References [1] Decommissioning of <strong>Nuclear</strong> Power Plant and Research Reactors, Safety Guide No. WS-G-2.1, IAEA, Vienna, 1999 [2] Decommissioning of Medical, Industrial and Research Facilities, Safety Guide No. WS- G-2.2, IAEA, Vienna, 1999 [3] IAEA, Decommissioning Techniques for Research Reactors, Technical Report Series No. 373, IAEA, Vienna, 1994 [4] Regulations for the Safe Transport of Radioactive Material, 1996 edition, Safety Standards Series No ST-1, IAEA, Vienna, 1996 [5] Planning and Management for the Decommissioning of Research Reactors and other Small <strong>Nuclear</strong> Facilities, Technical Report Series No. 351, IAEA, Vienna, 1993 [6] Regulation for the Basic Norms for Radiation Protection, Decree of the Council of Ministers N o 189, July 30 2004, Promulgated in State Gazette No. 73, 2004 281 of 455 6
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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
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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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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
Page 256 and 257: 7. Electrical heater The external h
Page 258 and 259: Page 1 / 7 EVITA: a semi-open loop
Page 260 and 261: Page 3 / 7 Fig.1: EVITA fuel Genera
Page 262 and 263: Page 5 / 7 Challenges When operatin
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Page 266 and 267: Nuclear Research Institutes, and so
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Page 270 and 271: 18. May Training of operating perso
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Page 278 and 279: • Core - liable to full scale rep
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Page 286 and 287: 4. References [1] Wagner F.M., Knes
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Page 290 and 291: 3.3 Increasing power beyond current
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Page 294 and 295: The treatment consisted of simple i
Page 296 and 297: 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 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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