Published September 2004
| Version v1
Report
Modelling reactor kinetics using different sets of delayed neutron data
Creators
- 1. Institute for Physics and Power Engineering, Obninsk (Russian Federation)
Description
Some reactor kinetics mathematical modelling problems are considered in the framework of the standard 6-group delayed neutron constants (Keepin, ABBN, JENDL, ENDF/B6) with energy and isotope dependent precursor half-lives, and the new 8-group delayed neutron data (Spriggs, Campbell, Piksaikin) with 'universal' precursor decay constant (or half-life) groups identical for all isotopes and energies. (author)
Additional details
Publishing Information
- Imprint Title
- Articles translated from Journal Yadernye Konstanty (Nuclear Constants). Series: Nuclear Constants, Issue No. 1-2, 2003
- Imprint Pagination
- 96 p.
- Journal Page Range
- p. 17-35
- Report number
- INDC(CCP)--440
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36104945
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Numerical Data, Translation
- Descriptors DEI
- DELAYED NEUTRONS; EVALUATED DATA; HALF-LIFE; INTERPOLATION; MATHEMATICAL MODELS; NUCLEAR DATA COLLECTIONS; NUCLEAR DECAY; PRECURSOR; REACTOR KINETICS
- Descriptors DEC
- BARYONS; DATA; DECAY; ELEMENTARY PARTICLES; FERMIONS; FISSION NEUTRONS; HADRONS; INFORMATION; KINETICS; MATHEMATICAL SOLUTIONS; NEUTRONS; NUCLEONS; NUMERICAL DATA; NUMERICAL SOLUTION
Optional Information
- Notes
- Translated from Russian by the IAEA; 33 refs, 3 figs, 9 tabs