RRFM 2009 Transactions - European Nuclear Society

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THE SPENT FUEL STORAGE AT THE DALAT NUCLEAR RESEARCH REACTOR PHAM VAN LAM, NGUYEN NHI DIEN, LUONG BA VIEN, LE VINH VINH, HUYNH TON NGHIEM, NGUYEN MINH TUAN AND NGUYEN KIEN CUONG Nuclear Research Institute 01 Nguyen Tu Luc Street, Dalat, Vietnam ABSTRACT The Dalat Nuclear Research Reactor is a pool type research reactor which was reconstructed from the 250 kW TRIGA-MARK II reactor. The spent fuel storage was newly designed and installed. Next to the reactor pool in the same concrete shield structure, there is another pool for storage of spent fuel assemblies. It was the old bulk-shielding experimental tank, kept from the former TRIGA reactor. For the present reactor, this tank is coated with stainless steel and filled with demineralised water. The capacity of the storage is to contain 300 spent fuel assemblies. Fuel reloading has been executed by using LEU FA on 12 September, 2007. In the fuel reloading, the 8 HEU FAs with highest burnup were removed from the core and put in the interim spent fuel storage in reactor pool. After cooling, the spent HEU FAs will be transported to spent fuel storage. The spent fuel storage will be used for storage of all spent HEU FAs when full core conversion will be executed. This paper presents spent fuel storage and handling at the Dalat Nuclear Research Reactor. 1. Introduction The Dalat Nuclear Research Reactor (DNRR) is a pool type research reactor which was reconstructed from the 250 kW TRIGA-MARK II reactor. The reactor core, the control and instrumentation system, the primary and secondary cooling systems, the spent fuel storage as well as other associated systems were newly designed and installed. The vertical section of the reactor is shown in Figure 1. ~ 2000 mm Rotating top lid Pool tank Upper cylindrical shell ~ 6840 mm Extracting well Concrete shielding A Spent fuel storage tank (ex bulk-shielding experimental tank) Core Graphite Thermal column door Door plug Fig 1. Vertical section view of the reactor 424 of 455
The core was loaded with WWR-M2 fuel assemblies with 36% enrichment. The fuel assembly is shown in Figure 2. The reconstructed reactor reached its initial criticality in November 1983 with 69 fuel assemblies and attained its nominal power of 500 kW in February 1984. 35mm 11mm 22mm 32mm 865mm 600 2.5mm 0.9 0.7 0.9 Al U+Al Al Fig 2. Fuel assembly type WWR-M2 425 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
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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
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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
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,
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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
Page 396 and 397: etween CRPq specific process and IP
Page 398 and 399: aspect audits, mainly in relation t
Page 400 and 401: 1 2 3 4 5 6 7 8 9 A B C D E F G H F
Page 402 and 403: MCNP5 is capable of calculating ter
Page 404 and 405: Similar to the case of stainless st
Page 406 and 407: LEU FUEL DISPOSITION AT WWR-M REACT
Page 408 and 409: Tested fuel assembles are load in t
Page 410 and 411: The PNPI experience of tests with W
Page 412 and 413: CURRENT UTILIZATION AND LONG TERM S
Page 414 and 415: Uusimaa hospital district decided t
Page 416 and 417: FiR 1 has an important regional rol
Page 418 and 419: STUDYING OF INFLUENCE OF A NEUTRON
Page 420 and 421: Definition of crystal structure and
Page 422 and 423: Microhardness measurement shows, th
Page 426 and 427: 2. Interim storage of spent fuel On
Page 428 and 429: A rotating bridge crane of 3.6-ton
Page 430 and 431: In order to investigate the perform
Page 432 and 433: (a) (b) Fig. 2. (a) low and (b) hig
Page 434 and 435: (a) (b) (c) (d) (e) (f) Fig. 5. TEM
Page 436 and 437: Spot Al Si Mo U Zr G 90.6 7.8 0.6 0
Page 438 and 439: volume in the material, which affec
Page 440 and 441: THE STEREOMETRIC ANALYSIS OF GAS PO
Page 442 and 443: of the crack of pillowing). It show
Page 444 and 445: One gets the impression that during
Page 446 and 447: switch from a fast to a thermal spe
Page 448 and 449: He production to fission ratio vs t
Page 450 and 451: INSPECTION EXPERIENCE WITH IEA-R1 S
Page 452 and 453: camera system, received from IAEA i
Page 454: core in the beginning 2007 (IEA-174
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