Checking and improvements of the multigroup data library EURLIB-4
Creators
- 1. Stuttgart Univ. (TH) (Germany, F.R.). Inst. fuer Kernenergetik und Energiesysteme
Description
Multigroup data libraries, which are widely distributed and used in many projects, must be checked properly before release. The zero version calculated with given flux weighting from evaluated nuclear data files is checked automatically by consistency tests in particle and energy transfer as far as possible. For EURLIB two data sets are produced with different processing codes independently at EURATOM/Ispra and at IKE/Stuttgart, so that a good check is given. With the help of several generic shielding problems the differences to US and Japanese group data sets have been studied in detail showing the effect of other group structures or other concepts of resonance weighting. It is shown that an improved treatment of thermal neutrons is very important. Finally the cross section requirements for deep penetration in iron are discussed. The present status of the library is presented
Additional details
Publishing Information
- Publisher
- OECD.
- Imprint Place
- Paris, France
- ISBN
- 92-64-2118-3
- Imprint Title
- Proceedings of specialist's meeting on nuclear data and benchmarks for reactor shielding, Paris, 27-29 October 1980
- Imprint Pagination
- 432 p.
- Journal Page Range
- p. 19-33.
Conference
- Title
- Specialist's meeting on nuclear data and benchmarks for reactor shielding.
- Dates
- 27 - 29 Oct 1980.
- Place
- Paris, France.
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 12616461
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPILED DATA; CONCRETES; E CODES; EVALUATED DATA; GAMMA DOSIMETRY; GUNDREMMINGEN-2 REACTOR; INTEGRAL CROSS SECTIONS; MULTIGROUP THEORY; NEUTRON DOSIMETRY; NEUTRON FLUX; NEUTRON SPECTRA; PHYSICAL RADIATION EFFECTS; SHIELDING MATERIALS
- Descriptors DEC
- BUILDING MATERIALS; BWR TYPE REACTORS; COMPUTER CODES; CROSS SECTIONS; DATA; DOSIMETRY; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; RADIATION EFFECTS; RADIATION FLUX; REACTORS; SPECTRA; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS