Least-squares calculation of the contribution of fissile nuclides to the general energy liberation in irradiated nuclear fuel

Journal Article · Sun Feb 01 04:00:00 EST 1987 · Sov. At. Energy (Engl. Transl.); (United States)

OSTI ID:5198173

Dubasov, Yu V; Khramov, N N

The authors consider the possibility of estimating the contribution of each fissile nuclide to the total energy liberation on account of the difference in product yields in the burnup of different nuclides. The total number of nuclei of each fission product is determined by the relation between the numbers of fissions of /sup 235/U, /sup 239/Pu, /sup 241/Pu, and /sup 238/U and the yields of each fission product in the fission of these nuclei. Solving a system of several related equations by the least squares method results in a quantitative estimation of the energy spectra of each of the fissile nuclides. The sensitivity and accuracy of the equations are tested against measured data for three-year service of WWER-440 reactor fuel with the following fission products: Sr 89, Zr 92, 93, and 94, Mo 97, 98, and 100, Ba 138, La 139, Ce 140 and 142, and Nd 145, 146, 148, and 150.

• OSTI ID: 5198173
• Journal Information: Sov. At. Energy (Engl. Transl.); (United States), Journal Name: Sov. At. Energy (Engl. Transl.); (United States) Vol. 61:2; ISSN SATEA
• Country of Publication: United States
• Language: English

Related Subjects

050700* -- Nuclear Fuels-- Fuels Production & Properties
050800 -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
653006 -- Nuclear Theory-- Spontaneous & Induced Fission
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ALKALINE EARTH ISOTOPES
BARIUM 138
BARIUM ISOTOPES
BARYON REACTIONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BURNUP
CERIUM 140
CERIUM 142
CERIUM ISOTOPES
DAYS LIVING RADIOISOTOPES
ENERGY SOURCES
ENERGY SPECTRA
ENRICHED URANIUM REACTORS
EVEN-EVEN NUCLEI
EVEN-ODD NUCLEI
FISSILE MATERIALS
FISSION
FISSION PRODUCTS
FISSIONABLE MATERIALS
FUEL CYCLE
FUELS
FUNCTIONS
HADRON REACTIONS
INTERMEDIATE MASS NUCLEI
IRRADIATION
ISOTOPES
LANTHANUM 139
LANTHANUM ISOTOPES
LEAST SQUARE FIT
MATERIALS
MATHEMATICAL MODELS
MAXIMUM-LIKELIHOOD FIT
MOLYBDENUM 100
MOLYBDENUM 97
MOLYBDENUM 98
MOLYBDENUM ISOTOPES
NEODYMIUM 145
NEODYMIUM 146
NEODYMIUM 148
NEODYMIUM 150
NEODYMIUM ISOTOPES
NEUTRON REACTIONS
NUCLEAR FUELS
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
NUMERICAL SOLUTION
ODD-EVEN NUCLEI
PLUTONIUM 239 TARGET
PLUTONIUM 241 TARGET
POWER REACTORS
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOISOTOPES
RARE EARTH ISOTOPES
RARE EARTH NUCLEI
REACTOR MATERIALS
REACTORS
SENSITIVITY ANALYSIS
SPECTRA
STABLE ISOTOPES
STRONTIUM 89
STRONTIUM ISOTOPES
TARGETS
THERMAL REACTORS
URANIUM 235 TARGET
URANIUM 238 TARGET
WATER COOLED REACTORS
WATER MODERATED REACTORS
WEIGHTING FUNCTIONS
WWER TYPE REACTORS
WWER-3 REACTOR
YEARS LIVING RADIOISOTOPES
YIELDS
ZIRCONIUM 92
ZIRCONIUM 93
ZIRCONIUM 94
ZIRCONIUM ISOTOPES