Assessment of nuclear concentration uncertainties in isotope kinetics by the interval calculation method
- 1. Obninsk State Technical Univ. for Nuclear Power Engineering (Russian Federation)
Description
Basically, the problem of dependency fuel cycle characteristic uncertainties from group constants and decay parameters uncertainties can be solved (to some extent) as well by use of sensitivity analysis. However such procedure is rather labor consuming and does not give guaranteed estimations for received parameters since it works, strictly speaking only for small deviations cause it is initially based on linearization of the mathematical problems. Suggested and realized technique of fuel cycle characteristic uncertainties estimation is based on so-call interval analysis (or interval calculations). The basic advantage of this technique is the opportunity of deriving correct estimations. In a professional terms this decision consist on introduction of a new special type of data such as Interval data in a codes and definition from them all arithmetic operations. Interval type data are in a real practice operation and use now. There are many realizations of interval arithmetic implemented by different ways. (orig.)
Additional details
Additional titles
- Original title (English)
- Jahrestagung Kerntechnik 2008. Tagungsbericht
Publishing Information
- Publisher
- Inforum Verlag
- Imprint Place
- Bonn (Germany)
- Imprint Title
- Annual meeting on nuclear technology 2008. Proceedings
- Imprint Pagination
- 886 p.
- Journal Page Range
- p. 30-37
Conference
- Title
- 2008 annual meeting on nuclear technology
- Original Conference Title
- Jahrestagung Kerntechnik (JK) 2008
- Dates
- 27-29 May 2008
- Place
- Hamburg (Germany)
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 42017003
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CROSS SECTIONS; DATA COVARIANCES; FUEL CYCLE; GROUP CONSTANTS; MIXED OXIDE FUELS; NEUTRON CAPTURE THERAPY; NEUTRON REACTIONS; ONE-GROUP THEORY; PERTURBATION THEORY; PLUTONIUM 241; PLUTONIUM 243; RADIONUCLIDE KINETICS; REACTOR PHYSICS; SENSITIVITY ANALYSIS
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; BARYON REACTIONS; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CROSS SECTIONS; ENERGY SOURCES; EVEN-ODD NUCLEI; FUELS; HADRON REACTIONS; HEAVY NUCLEI; HOURS LIVING RADIOISOTOPES; ISOTOPES; KINETICS; MATERIALS; MEDICINE; NEUTRON THERAPY; NEUTRON TRANSPORT THEORY; NUCLEAR FUELS; NUCLEAR MEDICINE; NUCLEAR REACTIONS; NUCLEI; NUCLEON REACTIONS; PHYSICS; PLUTONIUM ISOTOPES; RADIOISOTOPES; RADIOLOGY; RADIOTHERAPY; REACTOR MATERIALS; SOLID FUELS; SPONTANEOUS FISSION RADIOISOTOPES; THERAPY; TRANSPORT THEORY; YEARS LIVING RADIOISOTOPES
Optional Information
- Notes
- Imprint:Jahrestagung Kerntechnik 2008. Tagungsbericht