Several applications of J1 unfolding method of multiple foil data to reactor dosimetry
Description
With a view to prepare input data relating to uncertainties of guess-spectra for practical J1 unfolding calculations in a multi-group method, basic properties of neutron spectra are discussed and there are shown two interesting facts, which are the importance to specify the energy resolution to represent the spectrum uncertainties and the appearance of additional uncertainties of group averaged cross-sections due to their spectrum uncertainties wich are used as averaging spectrum. Through considering these facts, it has disappeared some peculiar dependency of final solutions on the computational group structure. Numerical examples of this multi-group J1 unfolding method are shown with some sensitivity analysis results and some discussions on the role of standard neutron fields are also presented
Additional details
Publishing Information
- ISBN
- 92-825-1868-X
- Imprint Title
- Dosimetry methods for fuels, cladding and structural materials
- Imprint Pagination
- 642 p.
- Journal Page Range
- p. 751-762.
- Report number
- EUR--6813(v.2)
Conference
- Title
- 3. ASTM-EURATOM symposium on reactor dosimetry.
- Dates
- 1 - 5 Oct 1979.
- Place
- Ispra, Italy.
INIS
- Country of Publication
- European Commission (EC), Brussels (Belgium)
- Country of Input or Organization
- European Commission (EC), Brussels (Belgium)
- INIS RN
- 12589484
- Subject category
- S99: GENERAL AND MISCELLANEOUS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; ERRORS; NEUTRON DOSIMETRY; NEUTRON FLUX; NEUTRON SPECTRA; SPECTRA UNFOLDING
- Descriptors DEC
- DATA PROCESSING; DOSIMETRY; RADIATION FLUX; SPECTRA