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Prokhorov, V.I.; Makarov, O.Yu.
5. Interbranch conference on reactors materials. Summaries of reports1997
5. Interbranch conference on reactors materials. Summaries of reports1997
AbstractAbstract
No abstract available
Original Title
Radiatsionnoe uprochnenie-okhrupchivanie stalej i splavov nekotorykh klassov pri temperature 300 deg C
Primary Subject
Secondary Subject
Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 166 p; ISBN 5-85165-354-X; ; 1997; p. 87; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
Record Type
Book
Literature Type
Conference
Country of publication
ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HARDENING, IRON ALLOYS, IRON BASE ALLOYS, IRRADIATION REACTORS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATERIALS TESTING REACTORS, MECHANICAL PROPERTIES, PHYSICAL RADIATION EFFECTS, POWER REACTORS, RADIATION EFFECTS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, TANK TYPE REACTORS, TEMPERATURE RANGE, TENSILE PROPERTIES, THERMAL REACTORS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
Reference NumberReference Number
Related RecordRelated Record
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AbstractAbstract
[en] An attempt is made to explain various swelling of the BOR-60 reactor fuel cans irradiated in the same fuel packet under identical conditions. Studies on the effect of different factors as possible causes of dispersions in the can swelling of identical fuel elements have shown that the most important factor is various gas content in the 0Kh16N15M3BR steel fuel can in the process of void formation
Original Title
Temperaturnaya zavisimost' parametrov radiatsionnoj poristosti obolochek tvehlov iz stali 0Kh16N15M3BR
Primary Subject
Secondary Subject
Source
Gosudarstvennyj Komitet po Ispol'zovaniyu Atomnoj Ehnergii SSSR, Moscow; Tsentral'nyj Nauchno-Issledovatel'skij Inst. Informatsii i Tekhniko-Ehkonomicheskikh Issledovanij po Atomnoj Nauke i Tekhnike, Moscow (USSR); p. 334-344; 1978; p. 334-344; Conference on reactor materials science; Alushta, Ukrainian SSR; 29 May - 1 Jun 1978; 3 refs.; 7 figs.; 1 table.
Record Type
Miscellaneous
Literature Type
Conference
Report Number
Country of publication
ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, DEFORMATION, DISTRIBUTION, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FLUIDS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, MOLYBDENUM ALLOYS, NICKEL ALLOYS, POWER REACTORS, RADIATION EFFECTS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, STAINLESS STEELS, STEELS, TRANSITION ELEMENT ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The generalized results of electron microscopic research and analysis of s-n diagrams of irradiated and nonirradiated specimens of iron, 18-10 and 16-15 steels, nickel and nickel-base alloys, mechanisms of radiation strengthening and high-temperature radiation embrittlement(HTTRE) are considered. HTTRE absebce in monocrystals is noted. The conclusion is made that HTTRE value in actual materials depends on alloying grain, size, nature of excessive phase precipitations, i.e. those factors which change the ratio between the strength of grain body and its boundaries. The mechanism of formation of radiation imperfections, accumulation of vacancy defects inside the grain , appearance of matrix(interstitial) dislocation loops and loops of vacancy nature on twin bounderies are considered. These defects prevent plastic material flow and bring about its stengthening
Original Title
Mekhanizmy radiatsionnogo uprochneniya i vysokotemperaturnogo radiatsionnogo okhrupchivaniya
Primary Subject
Source
Bannykh, O.A. (ed.); AN SSSR, Moscow. Inst. Metallurgii; p. 56-81; 1987; p. 56-81; Nauka; Moscow (USSR); 147 refs.; 54 figs.; 11 tabs.
Record Type
Book
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Prokhorov, V.I.; Makarov, O.Yu.; Rogozyanov, A.Ya.
5. Interbranch conference on reactors materials. Summaries of reports1997
5. Interbranch conference on reactors materials. Summaries of reports1997
AbstractAbstract
No abstract available
Original Title
Posleradiatsionnaya vyazkost' razrusheniya korpusnoj stali 15Kh2MFA po ispytaniyam kompaktnykh obraztsov C-F(T)12/24
Primary Subject
Source
Ministerstvo Rossijskoj Federatsii po Atomnoj Ehnergii, Moscow (Russian Federation); Gosudarstvennyj Nauchnyj Tsentr Rossijskoj Federatsii Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (Russian Federation); 166 p; ISBN 5-85165-354-X; ; 1997; p. 83; 5. Interbranch conference on reactor materials; 5. Mezhotraslevaya koferentsiya po reaktornomu materialovedeniyu; Dimitrovgrad (Russian Federation); 8-12 Sep 1997
Record Type
Book
Literature Type
Conference
Country of publication
Reference NumberReference Number
Related RecordRelated Record
INIS VolumeINIS Volume
INIS IssueINIS Issue
Votinov, S.N.; Prokhorov, V.I.; Kolesnikov, A.N.
Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Melekess (USSR)1973
Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Melekess (USSR)1973
AbstractAbstract
No abstract available
Original Title
K otsenke radiatsionnoj povrezhdaemosti zheleza, niobiya i molibdena pri nejtronnom obluchenii v reaktorakh SM-2 i BOR-60
Primary Subject
Source
1973; 24 p; 12 refs.
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Balashov, V.D.; Votinov, S.N.; Prokhorov, V.I.
Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Melekess (USSR)1970
Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Melekess (USSR)1970
AbstractAbstract
No abstract available
Original Title
Vliyanie oblucheniya na mekhanicheskie svojstva G Ts K splavov sistemy Fe-Cr-Ni
Primary Subject
Source
1970; 26 p; 4 references.
Record Type
Report
Report Number
Country of publication
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Methods and results of research on radiation changes in the hexagonal lattices of the BOR-60 reactor research assembly induced by internal gas pressure are presented. The sample tested was a typical lattice element for materials research in the BOR-60 reactor made of stainless steel containing 1.6% nickel, 1.5% manganese, 0.3% boron, and no chromium. Stress was created in the lattice by internal helium pressure. The basic parameters under study--the dimensions of the keylike lattice and the main diagonal of the hexagon cross section--were remotely measured both before and after irradiation with a micrometer. No noticeable buckling or warping of the cladding tube was detected during a visual inspection of the hexahedron being investigated. Measurements also pointed to the absence of swelling. The maximum increase in the dimension of the keylike lattice element, from its nominal value of 44.00 mm, was approximately 1.4 mm. The modulus of radiation creep was calculated using the method of least squares for temperature intervals of 610-615, 640-660, 685-705, and 725-7500K and for 770K
Primary Subject
Secondary Subject
Source
Translated from Atomnaya Energiya; 63: No. 4, 240-242(Oct 1987). Cover-to-cover translation of Atomnaya Ehnergiya (USSR).
Record Type
Journal Article
Literature Type
Translation
Journal
Country of publication
ALLOYS, BREEDER REACTORS, CARBON ADDITIONS, DEFORMATION, ELEMENTS, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATERIALS, MAXIMUM-LIKELIHOOD FIT, MECHANICAL PROPERTIES, NONMETALS, NUMERICAL SOLUTION, POWER REACTORS, RADIATION EFFECTS, RARE GASES, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, STEELS, TESTING
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] Behaviour of some heat resistant iron- and nickel base alloys under irradiation in BOR-60 and SM-2 reactors is considered. Comparison of radiation effects on high temperature ductility od steels and alloys with various type strengthening phases testifies to the fact that materials strengthened by γ-phase precipitates tend to high temperature rradiation-induced embrittlement to a greater degree that ones strengthened by carbides and Laves phases w
Original Title
Mekhanicheskie svojstva pri razlichnykh temperaturakh i struktura nerzhaveyushchikh stalej posle oblucheniya
Primary Subject
Source
Bannykh, O.A. (ed.); AN SSSR, Moscow. Inst. Metallurgii; p. 12-42; 1987; p. 12-42; Nauka; Moscow (USSR); 147 refs.; 54 figs.; 11 tabs.
Record Type
Book
Country of publication
ALLOYS, BREEDER REACTORS, CRYSTAL DEFECTS, CRYSTAL STRUCTURE, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, EXPERIMENTAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, HARDENING, IRRADIATION REACTORS, LINE DEFECTS, LIQUID METAL COOLED REACTORS, LMFBR TYPE REACTORS, MATERIALS TESTING REACTORS, MECHANICAL PROPERTIES, PHYSICAL RADIATION EFFECTS, POWER REACTORS, RADIATION EFFECTS, REACTORS, RESEARCH AND TEST REACTORS, SODIUM COOLED REACTORS, TANK TYPE REACTORS, TENSILE PROPERTIES, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, ZONES
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
AbstractAbstract
[en] The behaviour of irradiated steels of the 18-10, 16-15, 16-35 type and high-nikel alloys during high-temperature tests under loading is analyzed. The results of inpile and post-irradiation tests of tube samles are generalized. The conclusion is made that tests after irradiation are not representative for the estimation of creep rate and time to fracture for chromium-nickel steels of the 18-9 and 18-10 types in the temperature range of 500-600 deg C. For the temperature range of 650-700 deg C the tests under irradiation and after it show approximately similar values of high-temperature strength. Nickel-based alloys such as O3Kh17N77TYuR for example, with higher strength in nonirradiated state that steels during irradiation at high temperature retain the strength only in the case of small time to fracture (about 200 g). At higher time to fracture materials with a more stable structure are recommended ( steels of the 18-10 and 16-15 type)
Original Title
Povedenie obluchennykh stalej pri dlitel'nykh ispytaniyakh pod nagruzkoj
Primary Subject
Source
Bannykh, O.A. (ed.); AN SSSR, Moscow. Inst. Metallurgii; p. 43-55; 1987; p. 43-55; Nauka; Moscow (USSR); 147 refs.; 54 figs.; 11 tabs.
Record Type
Book
Country of publication
ALLOYS, AUSTENITIC STEELS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION RESISTANT ALLOYS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ALLOYS, IRON BASE ALLOYS, MECHANICAL PROPERTIES, MOLYBDENUM ALLOYS, NICKEL ALLOYS, NIOBIUM ADDITIONS, RADIATION EFFECTS, STAINLESS STEELS, STEELS, TITANIUM ADDITIONS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
Prokhorov, V.I.; Fin'ko, A.G.; Mineev, R.I.
Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR)1977
Nauchno-Issledovatel'skij Inst. Atomnykh Reaktorov, Dimitrovgrad (USSR)1977
AbstractAbstract
[en] To develop a technique for mechanical tests of fuel and absorbing element claddings, tensile tests have been carried out of irradiated and nonirradiated ring samples out of the 0Kh16N15M3B and 00Kh16N15M3B steels, 00Kh20N40B, Zr+1 % Nb and Zr+2,5% Nb alloys. The samples are irradiated by a fluence of fast neutrons 1x1021 n/cm2 with an energy higher than 0,85 MeV in the temperature range of 70 deg to 650 deg C. Empirical formula for the sample gauge length has been obtained as its direct measurement is impossible due to ununiform deformation over the ring sample length. It is shown that the test results depend to a great extent on the sample size, configuration and diameters of supports and the formula used for the gauge length determination. So for comparison of material deformability on the basis of ring sample tests these parameters should be taken into consideration. It is recommended that semicircular supports should be used with diameter being equal to 80-95 % of the sample internal diameres. For low-ductility material test prcautions should be taken not to use semicircular supports with shearings-off as well as with a diameter considerably less than the ring diameter
Original Title
Ehksperimental'noe opredelenaie rabochej dliny kol'tsevykh obraztsov iz obolochek TVEhLov pri poperechnom rastyazhenii
Primary Subject
Secondary Subject
Source
1977; 24 p; 6 refs.; 6 figs.; 3 tables.
Record Type
Report
Report Number
Country of publication
ALLOYS, CARBON ADDITIONS, CHROMIUM ALLOYS, CHROMIUM STEELS, CHROMIUM-MOLYBDENUM STEELS, CHROMIUM-NICKEL STEELS, CONFIGURATION, CORROSION RESISTANT ALLOYS, DIAGRAMS, ENERGY RANGE, INFORMATION, IRON ALLOYS, IRON BASE ALLOYS, KEV RANGE, MATERIALS TESTING, MOLYBDENUM ALLOYS, NICKEL ALLOYS, RADIATION EFFECTS, STAINLESS STEELS, STEELS, TESTING, TRANSITION ELEMENT ALLOYS, ZIRCONIUM ALLOYS
Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue
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