Studying of Influence of neutron irradiation on element ... · alloys SAV -1 and AMG -2 have face-centered cubic arrangement with lattice parameter, a = 4.066 ±0.003 Å and a = 4.0726

Studying of Influence of neutron Studying of Influence of neutron irradiation on element contents and irradiation on element contents and structures of aluminum alloys SAVstructures of aluminum alloys SAV--1 1

and AMGand AMG--2.2.

““Research Reactor Application for Materials Under High Neutron FlResearch Reactor Application for Materials Under High Neutron Fluenceuence””(TM(TM--34779)34779)IAEA IAEA -- Vienna, Austria, 17Vienna, Austria, 17--21 November 200821 November 2008

By S. Baytelesov

INSTITUTE OF NUCLEAR PHYSICSUZBEKISTAN ACADEMY OF SCIENCES


�� 1956 1956 -- Establishment of INP of Academy of Establishment of INP of Academy of SciencesSciences

�� 1959 1959 –– Research reactor &Research reactor & gamma facility started gamma facility started itit’’s operations operation

�� 19641964 -- CyclotronCyclotron УУ--150150--began workingbegan working�� 1976 1976 -- Government EnterpriseGovernment Enterprise ««RadiopreparatRadiopreparat»»was createdwas created�� 19901990 -- Scientific Industrial EnterpriseScientific Industrial Enterprise««TezlatgichTezlatgich»» was establishedwas established

�� 1995 1995 -- CyclotronCyclotron УУ--115115 was buildwas build

History

CyclotronCyclotron –– УУ150150Nuclear reactor WWRNuclear reactor WWR--SMSM

Cyclotron – У115 Gamma facilityNeutron generator

Nuclear Facilities

Developed TechnologiesDeveloped Technologies�� I. Cyclotrons I. Cyclotrons radionuclidesradionuclides::

CoCo--57, Zn57, Zn--65, Ga65, Ga--67, Ge67, Ge--68, Pd68, Pd--103, Ce103, Ce--139139•• II. II. Reactors Reactors radionuclidesradionuclides::

PP--32, P32, P--33, S33, S--35, Cr35, Cr--51, Mn51, Mn--54,54, FeFe--55, Co55, Co--58, Co58, Co--60, Mo60, Mo--99, Y99, Y--90, I90, I--125, I125, I--131, Pm131, Pm--147, Ta147, Ta--182, W182, W--188 188

•• III. III. Generators of Generators of radionuclide radionuclide ::GeGe--68 68 →→ GaGa--68, Mo68, Mo--99 99 →→ TcTc--99m, Sn99m, Sn--113 113 → → InIn--113m W113m W--

188 188 →→ ReRe--188188Planned for futurePlanned for future

IrIr--192, 192, 153Sm, 153Sm, LuLu--177, Cs177, Cs--131, Fe131, Fe--5959

WWRWWR--SM ReactorSM Reactor

�� Material scienceMaterial science�� Activation analysisActivation analysis, , RadiochemistryRadiochemistry�� Nuclear physicsNuclear physics�� Nuclear spectroscopyNuclear spectroscopy�� Radioisotopes productionRadioisotopes production• Irradiation of natural minerals• TESTING NEW FUEL ASSEMBLIES• Personnel training and education

�� Power 10 MWPower 10 MW�� Maximal thermal neutron in Maximal thermal neutron in

BeBe--re flux 2re flux 2��101014 14 nn��smsm22//ss..�� Fast in Be re 5Fast in Be re 5��10101133 nn��smsm22//ss..�� Max fast in FA Max fast in FA -- 10101144 nn��smsm22//ss..�� Vertical channels Vertical channels –– 43,43,�� HorizontalHorizontal –– 9.9.�� Thermal columnThermal column--11�� Exploitation of the reactor Exploitation of the reactor

WWRWWR--SM was planned till SM was planned till 2022.2022.

Reactor operation hours

01000200030004000500060007000

1959

1963

1967

1971

1975

1979

1983

1987

1991

1996

2000

2004

23.05.20

08


Taking into consideration development of Taking into consideration development of international programs for reduction of fuel international programs for reduction of fuel enrichment in research reactors, it was enrichment in research reactors, it was decided to convert the WWRdecided to convert the WWR--SM reactor from SM reactor from IRTIRT--3M (36% enriched) fuel to IRT3M (36% enriched) fuel to IRT--4M 4M (19.7% enriched) fuel(19.7% enriched) fuel. .

HEU(36%) IRT-3M LEU (19.7%) IRT-4M

Parameter 6-Tube IRT-3M

6-Tube IRT-4M

Dispersant UO2-Al UO2-Al Wt. % 235U 36.0 19.7 (gU/cm3)meat 2.5 2.8 VFD, % 28.5 31.7 235U/FA, g 309 266 Hmeat, cm 60 60 Tmeat, mm 0.50 0.70 Tclad, mm 0.45 0.45 Tcoolant, mm 2.05 1.85 Volmeat, cm3 342 481 Temperature clad 100 °C 98 °C

Conversion of WWR-SM reactor from use of HEU fuel to use of LEU fuel

Active core model of the WWRActive core model of the WWR--SM SM reactorreactor


IRT-2D, WIMS, MCNP-4C, PLTEMP and PARET codes were used for analyses.

Description of monitorsDescription of monitors

12,251173,2(100)1332,5(100)

5,26y626,23Ni60(np)Co60

5.9842898(92)1836,1(100)

108,1d1210089Y(n,2n)88Y9,05834,8(100)312,6d35,84Fe54(n,p) Mn54

15.15889,2(100)1120,5(100)

83,89d4.57,93Ti46(n,p)Sc46

15.151312,1(100)1037,4(100)983,5(100)

1,83d773,9448Ti(n,p)48Sc1.14571368,5(100)15,05h6,378,724Mg(n,p)24Na12,25810,8(99)71,3d2,667,8858Ni(n,p)58Co52.7d100197Au(n,γ)198AuM,mgЕ, KeVT1/2Еп, MeV%

Experiment results of fast neutron Experiment results of fast neutron flux in the reactor (Niflux in the reactor (Ni--58, optical 58, optical

absorption) absorption)

1.6510.366-7101.5712.036-291.4417.524-281.524.982-471.1510.027-361.1810.123-750.964.156-140.96.395-130.654.784-120.41.897-11

optical absorptionNi-5810-12

# channels#


Measurement of neutron flux Measurement of neutron flux spectrumspectrum

��Monitors Au, Co, Ni, Ti, Fe have been Monitors Au, Co, Ni, Ti, Fe have been made from thin roll flat metal foil, and Y made from thin roll flat metal foil, and Y and Mg were taken in the form of their and Mg were taken in the form of their connections MgO and Y2O3. connections MgO and Y2O3. ��Two sets of monitors have been Two sets of monitors have been weighed, packed into polyethylene weighed, packed into polyethylene packages, wrapped in aluminum foil and packages, wrapped in aluminum foil and soldered in quartz ampoules. One of soldered in quartz ampoules. One of ampoules has been soldered in ampoules has been soldered in CdCd glass glass for cutfor cut--off by component thermal flux in off by component thermal flux in the course of irradiation of monitors. the course of irradiation of monitors. Irradiation of both containers was carried Irradiation of both containers was carried out consistently in the current of 2 hours out consistently in the current of 2 hours in the second channel of the reactor in the second channel of the reactor general neutrons flux. Measurement of general neutrons flux. Measurement of samplessamples’’ gamma activity was carried out gamma activity was carried out in 3in 3--10 days after irradiation. 10 days after irradiation. Registration of samples gamma spectrum Registration of samples gamma spectrum was carried out on HP was carried out on HP GeGe detector with detector with multichannel analyzer DSA1000 of multichannel analyzer DSA1000 of Canberra firm, processing of gamma Canberra firm, processing of gamma spectrum was carried out by means of spectrum was carried out by means of standard software package Genie 2000.standard software package Genie 2000.

��Neutron flux n/smNeutron flux n/sm22*s*s

Neutron energy MeV


Calculation results neutron flux Calculation results neutron flux spectrumspectrum


3,30102E+14Total8,57388E+123,0000E+00 - 2,0000E+013,31201E+138,0000E-01 - 3,0000E+001,33735E+146,2500E-07 - 8,0000E-011,54672E+140 - 6,2500E-07

6-2


2-5


1-4

Flux n/sm2*sEnergy MeV# Channel

Definition of crystal structure and parameter of a lattice of Definition of crystal structure and parameter of a lattice of alloys was spent on Xalloys was spent on X--ray diffract meter DRONray diffract meter DRON--33ММ (l (l

=0.15418 nanometers).=0.15418 nanometers).�� According to the radiographic According to the radiographic analysis as expected, initial analysis as expected, initial alloys SAValloys SAV--1 and AMG1 and AMG--2 have 2 have faceface--centered cubic centered cubic arrangement with lattice arrangement with lattice parameter, parameter, a a = 4.066 = 4.066 ±± 0.003 0.003 ÅÅand a = 4.0726and a = 4.0726±±0.003 0.003 ÅÅ, , accordingly. Small increase of accordingly. Small increase of alloysalloys’’ lattice parameter in lattice parameter in comparison with the reference comparison with the reference aluminum sample (4.0414 aluminum sample (4.0414 ÅÅ) is ) is result from the presence of result from the presence of impurity in them. impurity in them.


Definition of element structure and metallographic analysis of iDefinition of element structure and metallographic analysis of investigated nvestigated samples was carried out in Xsamples was carried out in X--ray micro analyzer "ray micro analyzer "JeolJeol" JSM 5910 IV " JSM 5910 IV -- Japan. Japan. Relative contents of basic elements (in %) in handRelative contents of basic elements (in %) in hand--picked points of SAVpicked points of SAV--1 and 1 and AMGAMG--2 samples before and after irradiation with different fluences2 samples before and after irradiation with different fluences

1000,080,230,222,521,6895,27AMG-21000,010,332,350,4596,861020

n/sm2SAV-1

1000,080,240,242,161,8595,43AMG-21000,010,322,050,5397,091019

n/sm2SAV-1

1000,060,250,231,702,0295,74AMG2

1000,010,301,750,6297,321018n/sm2

SAV-11000,050,260,240,902,496,15AMG-21000,020,280,011,100,8297,771017 n/sm2SAV-11000,040,250,240,102,8096,57AMG-21000,020,140,010,501,0698,27NO IrSAV-1

totalС uFeMnSiMgА1samples


�� From the table it is clear, that after From the table it is clear, that after irradiation various fluence irradiation various fluence redistribution of concentration of redistribution of concentration of basic elements in the chosen points basic elements in the chosen points is observed. is observed. �� Smashing and dispersion of local Smashing and dispersion of local insoluble intermetallic phases under insoluble intermetallic phases under reactor influence to radiation, finally reactor influence to radiation, finally leads to essential change of element leads to essential change of element structure in the measured points, as structure in the measured points, as it is shown in the table. it is shown in the table.


StructureStructure SAVSAV--11, , not irradiatednot irradiatedIn raster pictures of In raster pictures of basic elements basic elements before irradiation it before irradiation it is shown their nonis shown their non--uniform distribution uniform distribution on all volume of on all volume of alloys where local alloys where local formations in the formations in the form of white stains form of white stains insoluble insoluble intermetallicintermetallic phases phases of system Alof system Al--MgMg--SiSi--Fe with the sizes 1Fe with the sizes 1÷÷10 10 mkmmkm..


Microstructure of SAVMicrostructure of SAV--1 alloy after 1 alloy after irradiation with 10irradiation with 101919 n/smn/sm22 fluencefluence

According to the analysis of raster According to the analysis of raster pictures of basic elements, after pictures of basic elements, after irradiation to fluences 10irradiation to fluences 1019 19 n/smn/sm22 local local insoluble intermetallic system Alinsoluble intermetallic system Al--MgMg--SiSi--Fe phases are shattered and dissipate on Fe phases are shattered and dissipate on the sample, becoming practically uniform. the sample, becoming practically uniform. Especially on raster pictures of elements Especially on raster pictures of elements Mg and Si. After irradiation fluence 10Mg and Si. After irradiation fluence 1019 19

n/ smn/ sm22 the sizes of intermetallic system the sizes of intermetallic system AlAl--MgMg--SiSi--Fe phases become not more Fe phases become not more than 0, 5than 0, 5--2mkm. 2mkm.


�� Apparently, after irradiation ageing Apparently, after irradiation ageing process is slowed essentially down process is slowed essentially down because of steady dislocation grids because of steady dislocation grids formed at the expense of scattered micro formed at the expense of scattered micro inclusions and radiating defects. From inclusions and radiating defects. From drawings it is clear, that after irradiation drawings it is clear, that after irradiation on surfaces of sample SAVon surfaces of sample SAV--1 the volume 1 the volume of oxide connections (stain of black color) of oxide connections (stain of black color) increases in comparison with not increases in comparison with not irradiated ones. Similar pictures are irradiated ones. Similar pictures are observed both for AMGobserved both for AMG--2 alloys. 2 alloys.


MicrohardnessMicrohardness measurementsmeasurements�� MicrohardnessMicrohardnessmeasurement shows, measurement shows, that it is observed strong that it is observed strong enough dependence enough dependence НН µµfrom weight to value F from weight to value F ≈≈3 N. On weights F> 3 N 3 N. On weights F> 3 N microhardnessmicrohardness practically practically does not depend on does not depend on weight. As depth of weight. As depth of penetration of diamond penetration of diamond pyramid depends on pyramid depends on weight, it is possible to weight, it is possible to draw a conclusion, that draw a conclusion, that in surface layer of in surface layer of samples at samples at microhardnessmicrohardness definition, definition, apparently plays apparently plays essential role. essential role.

Neutron irradiated SAVNeutron irradiated SAV--1 alloy samples1 alloy samples’’ microhardnessmicrohardness ((НН µµ) ) dependence weight on dependence weight on indentorindentor: not irradiated (1); irradiated by : not irradiated (1); irradiated by

fluences 10fluences 1018 18 smsm22 (3) and 10(3) and 101919 smsm22 (2)(2)

Weight F-Newton


Neutron irradiated AMGNeutron irradiated AMG--2 alloy samples2 alloy samples’’ microhardnessmicrohardness ((НН µµ) ) dependence from weight on dependence from weight on indentorindentor: not irradiated (1); irradiated : not irradiated (1); irradiated

by fluences 10by fluences 101818 cmcm22 (2) and 10(2) and 101919 cmcm22 (3)(3)


Weight F-Newton

MicrohardnessMicrohardness change of samples depending on change of samples depending on fluence in graphical view are resulted in drawing fluence in graphical view are resulted in drawing

microhardnessmicrohardnessEssentially increase of size after Essentially increase of size after irradiation fluence 10irradiation fluence 1017 17 n/smn/sm22 and and rather poorly linearly grows at the rather poorly linearly grows at the further increase fluence almost in further increase fluence almost in all range of weight F> 3 N, that all range of weight F> 3 N, that microhardnessmicrohardness essentially essentially increases at the first irradiation. increases at the first irradiation. Essential reduction of the sizes Essential reduction of the sizes (smashing) and dispersion of local (smashing) and dispersion of local insoluble intermetallic phases on insoluble intermetallic phases on big volume of alloys after big volume of alloys after irradiations and radiating defects, irradiations and radiating defects, on the visible lead to additional on the visible lead to additional fastening of dispositions that fastening of dispositions that causes increase in causes increase in microhardnessmicrohardnessof samples. of samples. ““Research Reactor Application for Materials Under High Neutron FlResearch Reactor Application for Materials Under High Neutron Fluenceuence””(TM(TM--34779)34779)

IAEA IAEA -- Vienna, Austria, 17Vienna, Austria, 17--21 November 200821 November 2008

AMG-2 and SAV-1 alloys microhardness dependence from neutron fluence. Points marked for comparison corresponding to Hµvalues of not irradiated AMG-2 and SAV-1

CConclusiononclusion� Influence of reactor irradiations various fluences (1017 -1021 n/sm2) on a microstructure and microhardness of alloys SAV-1 and AMG-2 is studied. It is revealed, that reactor irradiation leads to practically uniform redistribution of the basic impurity on all sample, before irradiation there was non-uniform distribution in initial samples because of natural ageing. � In the interval we have found fluence swelling is insignificant. � It is established, that under the influence of irradiation microhardness of alloys essentially increases at primary irradiation before fluence 1017 n/sm2 and linearly grows at the further increase fluences to 1021 n/sm2. The microhardness increase results from smashing and dispersion local insoluble intermetallic system Al-Mg-Si-Fe phases on great volume of alloys and growth of concentration of radiation defect with increase of fluence.““Research Reactor Application for Materials Under High Neutron FlResearch Reactor Application for Materials Under High Neutron Fluenceuence””(TM(TM--34779)34779)

IAEA IAEA -- Vienna, Austria, 17Vienna, Austria, 17--21 November 200821 November 2008

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Studying of Influence of neutron irradiation on element ... · alloys SAV -1 and AMG -2 have face-centered cubic arrangement with lattice parameter, a = 4.066 ±0.003 Å and a = 4.0726