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Kushneriuk, S.A.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1976
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1976
AbstractAbstract
[en] Numerous publications are cited, some with abstracts, on the subjects of ground water motion, neutron transport, and reactor physics. (E.C.B.)
Primary Subject
Source
Oct 1976; 23 p
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Report
Literature Type
Bibliography
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Kushneriuk, S.A.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1970
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1970
AbstractAbstract
No abstract available
Primary Subject
Source
Jan 1970; 67 p
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Report
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Love, M.D.; Kushneriuk, S.A.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1974
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs.1974
AbstractAbstract
No abstract available
Primary Subject
Source
May 1974; 101 p; 22 refs.
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Report
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Kushneriuk, S.A.; Lone, M.A.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1982
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1982
AbstractAbstract
[en] Formulae are presented for calculating the radial distributions and averages of the fluxes and currents of radiation on a plane, circular aperture due to direct contributions from a plane, uniformly distributed source of radiation of circular shape located co-axially with the aperture. The source emission is either isotropic or of the cosine type. Limiting forms of the fluxes and currents, the mean solid angle of emission from source to aperture and certain identities that arise are also discussed. Some graphical illustrations are given
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Source
Jun 1982; 36 p
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Report
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AbstractAbstract
No abstract available
Primary Subject
Record Type
Journal Article
Journal
Nuclear Science and Engineering; v. 51(1); p. 76-78
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Kushneriuk, S.A.; Wong, P.Y.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1983
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1983
AbstractAbstract
[en] Results are presented of neutronic evaluations of activations induced in foils irradiated at various positions within the INRS irradiation facility; comparisons with the results of measurements are made. In the measurements, DT-generated neutrons resulting from accelerated deuterium (60 keV) striking a tritiated target located at the centre of the facility were used. The activities considered were those induced via the 27Al(n,p)27Mg, 27Al(n,a)24Na, 63Cu(n,2n)62Cu, 127I(n,2n)126I, 90Zr(n,2n)89Zr, sup(115)In(n,γ)sup(116m)In, 197Au(n,γ)198Au, 232Th(n,γ)233Th and 232Th(n,f)89Rb (F.P.) reactions. The calculations were made using the MORSE Monte Carlo neutronics code in the 25-neutron-group approximation for determining the fluxes, and a specially prepared 25-neutron-group ΣactivitiesΣ library of reaction cross sections for determining the resultant reaction rates
Primary Subject
Source
Apr 1983; 57 p
Record Type
Report
Literature Type
Numerical Data
Report Number
Country of publication
ACTINIDE NUCLEI, ALPHA DECAY RADIOISOTOPES, ALUMINIUM ISOTOPES, BARYON REACTIONS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBON, COPPER ISOTOPES, CROSS SECTIONS, DATA, ELEMENTS, EVEN-EVEN NUCLEI, GOLD ISOTOPES, HADRON REACTIONS, HEAVY NUCLEI, HOURS LIVING RADIOISOTOPES, INDIUM ISOTOPES, INFORMATION, INTERMEDIATE MASS NUCLEI, IODINE ISOTOPES, ISOMERIC TRANSITION ISOTOPES, ISOTOPES, LIGHT NUCLEI, NONMETALS, NUCLEAR REACTIONS, NUCLEI, NUCLEON REACTIONS, NUMERICAL DATA, ODD-EVEN NUCLEI, RADIOISOTOPES, SECONDS LIVING RADIOISOTOPES, STABLE ISOTOPES, THORIUM ISOTOPES, YEARS LIVING RADIOISOTOPES, ZIRCONIUM ISOTOPES
Reference NumberReference Number
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Ells, C.E.; Kushneriuk, S.A.; Van Der Kuur, J.H.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1981
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1981
AbstractAbstract
[en] A vessel of type 316L stainless steel will be used for the long-term storage of tritium. The tritium may be gas, or fixed as a metal tritide. We have assembled the data and equations needed to estimate the efficiency of the containment. If the vessel wall is 6 mm thick, then at the design storage temperature, < 348 K, negligible tritium will be released by permeation through the vessel wall. In hypothetical accidents, the vessel and contents will be heated 2-12 h to temperatures up to 1073 K. Permeation of tritium through the vessel wall is very rapid at this temperature, although heating to 573 K would be of little concern. Techniques for estimating tritium loss from the vessel over the complete range of conditions envisaged are listed in the report
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Source
Mar 1981; 40 p
Record Type
Report
Report Number
Country of publication
ALLOYS, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBON ADDITIONS, CHROMIUM ALLOYS, CORROSION RESISTANT ALLOYS, HYDRIDES, HYDROGEN COMPOUNDS, HYDROGEN ISOTOPES, IRON ALLOYS, IRON BASE ALLOYS, ISOTOPES, LIGHT NUCLEI, NUCLEI, ODD-EVEN NUCLEI, RADIOISOTOPES, STAINLESS STEELS, STEELS, TITANIUM COMPOUNDS, TRANSITION ELEMENT ALLOYS, TRANSITION ELEMENT COMPOUNDS, YEARS LIVING RADIOISOTOPES, ZIRCONIUM COMPOUNDS
Reference NumberReference Number
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Kushneriuk, S.A.; Lone, M.A.; Hausser, O.; Wong, P.Y.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1983
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1983
AbstractAbstract
[en] The role of collision/escape probabilities in establishing the prompt response of bismuth germanate and NaI(Tl) scintillators is investigated. A possible approximation to the collision probability is discussed. Exact expressions for the probability of escape of radiation from finite, right circular cylindrical and rectangular parallelepiped-shaped detectors are derived from an exponential-like spatial distribution of the source in the detector medium and a parametrized angular distribution of emission of the source. Fairly extensive tables of collision probabilities calculated for these bodies are given. For purposes of comparison some results obtained previously in a Monte Carlo calculation are also presented and discussed
Source
Jun 1983; 53 p
Record Type
Report
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Kushneriuk, S.A.; Wong, P.Y.; Abel, G.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1979
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1979
AbstractAbstract
[en] Results are presented of evaluated neutron fluxes, and neutron induced activations of isotopes of Al, Fe, Co, Zr, Cu, Th, U and Pu in various graphite-thorium (metal) assemblies. The systems considered are spherically symmetric with the 14 MeV, DT neutron sources for the irradiation located at the system centre. The systems are idealizations of material arrangements in proposed experimental activation-analysis studies of graphite-thorium blankets. (author)
Primary Subject
Source
Feb 1979; 37 p
Record Type
Report
Literature Type
Numerical Data
Report Number
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Kushneriuk, S.A.; Wong, P.Y.
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1981
Atomic Energy of Canada Ltd., Chalk River, Ontario. Chalk River Nuclear Labs1981
AbstractAbstract
[en] Results of neutronic evaluations of fissile fuel breeding in a variety of DT fusion hybrid-reactor blankets are presented. The blankets are of the fast-fission or fission-suppressed rather than fission-enhanced designs, i.e. in the blankets considered emphasis is on fissile fuel rather than power production. For 233U breeding, when Li metal is the coolant for the first wall and the graphite moderator and the tritium breeding constituent of the blanket, the number of atoms of 233U produced per fusion in blankets that could be of practical interest is in the range 0.5 - 0.68, with the lower value applying to water-cooled ThO2 fertile fuel, the upper to gas-cooled Th-metal fuel located next to the reactor first wall. Neutron multipliers like Pb or Be can increase the production to about 0.74. For 239Pu breeding, the production ratio in practical blankets is 0.6 - 1.64, with the best results being for gas, Na- or Li-metal-cooled U-metal fuels located adjacent to the first wall (the U is depleted uranium). Gas-cooled U-Th-metal blankets, optimized for 233U breeding, yield 0.76 atoms of 233U and 0.38 atoms of 239Pu. The blanket energy multiplication factors are in the range 1.6 - 2.5 for Th blankets, 2.5 - 9.0 for U blankets and approximately 5.5 for the U-Th-metal blanket. The tritium breeding ratio in all blankets is 1.075. Blankets with other first wall, coolant and tritium breeding constituents are also considered. The fusion power requirements of hybrids that could supply the fuel needs of thorium-burning CANDU power reactors, and the allowed costs for building the hybrids are indicated
Primary Subject
Secondary Subject
Source
Nov 1981; 59 p
Record Type
Report
Literature Type
Numerical Data
Report Number
Country of publication
BERYLLIUM, BREEDING, BREEDING BLANKETS, BREEDING RATIO, CANDU TYPE REACTORS, CONSTRUCTION, COOLANTS, COST, DEUTERIUM, FERTILE MATERIALS, FISSILE MATERIALS, FLIBE, FUEL CYCLE, GRAPHITE, HYBRID REACTORS, LEAD, LITHIUM, MULTIPLICATION FACTORS, NEUTRON FLUX, PLUTONIUM 239, THEORETICAL DATA, THORIUM, THORIUM OXIDES, TRITIUM, URANIUM 233
ACTINIDE COMPOUNDS, ACTINIDE NUCLEI, ACTINIDES, ALKALI METALS, ALKALINE EARTH METALS, ALPHA DECAY RADIOISOTOPES, BETA DECAY RADIOISOTOPES, BETA-MINUS DECAY RADIOISOTOPES, CARBON, CHALCOGENIDES, CONVERSION RATIO, DATA, ELEMENTS, EVEN-ODD NUCLEI, FISSIONABLE MATERIALS, HEAVY NUCLEI, HEAVY WATER MODERATED REACTORS, HYDROGEN ISOTOPES, INFORMATION, ISOTOPES, LIGHT NUCLEI, METALS, MOLTEN SALTS, NONMETALS, NUCLEAR FUEL CONVERSION, NUCLEI, NUMERICAL DATA, ODD-EVEN NUCLEI, ODD-ODD NUCLEI, OXIDES, OXYGEN COMPOUNDS, PLUTONIUM ISOTOPES, POWER REACTORS, PRESSURE TUBE REACTORS, RADIATION FLUX, RADIOISOTOPES, REACTOR COMPONENTS, REACTORS, SALTS, STABLE ISOTOPES, THERMAL REACTORS, THORIUM COMPOUNDS, URANIUM ISOTOPES, YEARS LIVING RADIOISOTOPES
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