RRFM 2009 Transactions - European Nuclear Society

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1436 keV, Cs 138 1369 keV, Na 24 2. Experimental method During the normal operation of HANARO, the species and concentrations of the radionuclides in the primary coolant except for the short-lived nuclides were determined by using the gamma-ray spectroscopy. The primary coolant was collected at the entrance to the primary coolant purification system at a reactor power of 30 MW, the normal power of HANARO. The volume of the collected water was 100 cm 3 . The gamma-rays from the coolant water were detected by using the spectroscopy system of a coaxial HPGe detector with a relative efficiency of 15% [3,4]. The cooling time was 5 min., and the specific concentration of each nuclide in the coolant at the reactor core was obtained by considering the cooling time. The full-energy peak efficiency for the volume source was calibrated as a function of the photon energy for the HPGe detector. The efficiency calibration was carried out with a cylindrical bottle-type standard source which had a homogeneous radionuclide mixture in the matrix with the same shape as the sample bottle. The density of the matrix was 0.97 g/cm 3 . Fig. 1 shows the typical gamma-ray spectrum of the HANARO coolant water with a cooling time of 5 min. and a gamma-ray collection time of 30 min. During the normal operation of a water-cooled reactor, the major gamma-ray source in the coolant is N-16 generated by O 16 (n,p)N 16 reaction. It was confirmed that the effect of the N-16 gamma-rays on the spectrum was negligible through the gamma-ray spectrum obtained with the minimum amplification factor of the spectroscopy system since the cooling time was long enough for the N-16 nuclide to decay out. As shown in the figure, the gamma-ray peaks from Na-24, Mg-27 and Al-28 are much higher than those of other nuclides. Counts/unit energy 10 5 10 4 10 3 10 2 166 keV, Ba 139 250 keV, Xe 135 307 keV, Tc 101 844 keV, Mg 27 1294 keV, Ar 41 2754 keV, Na 24 10 1 0 500 1000 1500 2000 2500 3000 Energy [keV] Fig 1. Typical gamma-ray spectrum of HANARO coolant water with a cooling time of 5 min. and a collection time of 30 min. The species and concentrations of the radionuclides except for the short-lived nuclides in the primary coolant during the normal operation of HANARO were determined by using the full-energy peaks on the spectrum. Table 1 represents the determined concentrations of the confirmed radionuclides in the coolant water. Although very small gamma-ray peaks from several nuclides such as Ce-141, I-131 and Zr-95 were sometimes confirmed, the determination of their concentrations in the coolant was meaningless since their uncertainties were so large. When the sample was cooled for a long time, and the gamma-rays were collected for a long time, the Cs-137 and Co-60 peaks could be confirmed. The uncertainty in the determination for the activity concentration was below 1% for Na-24, Ma-27, Al-28 and Ar-41. The uncertainty for the fission product was relatively high, and it ranged from 5 to 25%. From the table, it is confirmed that the concentrations of Na-24, Mg-27, Al-28 and Ar-41 are much higher than those of other nuclides in the coolant, and they are 3×10 5 ~5×10 6 Bq/liter. In 320 of 455
addition, many fission products such as iodine and xenon nuclides were detected in the coolant. Among them, the concentrations of Rb-89, Xe-138 and Xe-133 were relatively higher than those of others, and they were ~3×10 4 Bq/liter. Xe-133 is a very important gaseous radionuclide source in the research reactor. Its concentration at the beginning of a reactor period is small and increases with the reactor operation time since its half-life is relatively long. The source of the fission products in the coolant during the normal operation was the surface contamination of the nuclear fuel by uranium in the fabrication procedure. However, in the abnormal condition like a fuel defect, the concentrations of the fission products will be increased abruptly. Tab 1: Determined concentrations of the radionuclides in the HANARO coolant water. Nuclide Al-28 Ar-41 Ba-139 Ba-141 Ce-141 Cs-138 I-131 I-132 I-133 I-134 I-135 Kr-85m Kr-87 Kr-88 La-142 Mg-27 Mn-56 Mo-101 Na-24 Nb-95 Half-life (min.) 2.31 109.8 83.06 18.267 46632.96 32.2 11579.04 142.8 1218 52.6 396.66 268.86 76.4 170.34 92.517 9.462 154.56 14.62 897.54 50364 Main gamma- Concentration ray energy (Bq/liter) (keV) 1778.8 1293.6 165.8 190.22 145.45 1435.86 364.48 667.69 529.5 1072.53 1260.41 151 402.7 2392.11 641.17 843.73 1811.2 590.82 1368.55 765.82 1.75E+06 3.15E+05 1.38E+04 1.58E+04 - 2.56E+04 - 7.17E+03 4.01E+03 - - 1.52E+03 - - - 5.25E+06 1.31E+04 - 1.54E+06 - Nuclide Np-239 Rb-88 Rb-89 Sr-91 Sr-92 Sr-93 Tc-101 Tc-104 Tc-99m Te-131 Te-131m Te-132 Te-133 Te-134 W-187 Xe-133 Xe-135 Xe-135m Xe-138 Zr-95 Half-life (min.) 3391.68 17.8 15.4 580.14 162.6 7.3 14.2 18.2 361.14 25 1800 4675.02 12.45 41.8 1434 7619.04 544.98 15.6 14.13 92733.12 Main gamma- Concentration ray energy (Bq/liter) (keV) 103.7 1836 1031.88 555.57 1383.9 590.9 306.86 357.99 140.51 149.72 852.21 228.16 312.1 565.99 685.74 81 249.79 526.81 258.31 724.18 6.13E+03 1.76E+04 3.09E+04 - 7.48E+03 - 1.95E+04 8.35E+03 4.73E+03 4.50E+03 - 1.70E+03 5.05E+03 - 3.20E+04 9.32E+03 6.90E+03 1.19E+03 2.45E+04 - 3. Origin of radionuclide in HANARO coolant water Activation products of the coolant water such as N-16, N-17 and O-19 were not detected in this measurement. The main gamma-ray sources in the coolant water after 5 min. cooling are Na-24, Mg-27 and Al-28. Their origins are radiative reactions of aluminum used as the structural material in the reactor core and the irradiation rigs and the cladding of the nuclear fuel. Ar-41 is generated from the activation of dissolved air. Mn-56 is an activation product of iron in stainless steel used as structural material. W-187 is also an activation product of tungsten used as welding rod. Zr-related nuclide such as Nb-95 can be generated as a fission product or from the activation of zirconium used in the flow tube and the fuel bundle. Various fission products such as iodine, xenon, etc. are detected in the coolant in spite of the normal operation. These nuclides are generated from the fission process of the uranium contaminated on the fuel surface. The maximum allowable surface contamination of HANARO fuel is 3.25 μg-U 235 /ft 2 . From the above result, it is confirmed that even a small amount of uranium contaminated on the fuel surface can give rise to large gamma-ray peaks of the fission products enough to determine their concentrations in the coolant. 4. Detection of fuel defect The concentrations of the radionuclides in the primary coolant were measured continually once a week during the reactor operation. The variation of the concentration of each nuclide was 321 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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Page 276 and 277: PARTIAL DISMANTLING OF RESEARCH REA
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
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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
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Page 344 and 345: • Removal of sludge from the SNF
Page 346 and 347: UPGRADED REACTOR SYSTEMS FOR ENHANC
Page 348 and 349: Parameter HEU LEU a 6.0x10 -5 (°K)
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
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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
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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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