The cross section library IRDF-90/NMF-G and its user-friendly processing for practical applications

Conference · Sat Dec 31 00:00:00 EST 1994

OSTI ID:62101

Szondi, E J; Zsolnay, E M ^[1]; Nolthenius, H J ^[2]

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1. Technical Univ., Budapest (Hungary)
2. Netherlands Energy Research Foundation, Petten (Netherlands)

The updated version of the International Reactor Dosimetry File, IRDF-90/NMF-G consists of data collected from different sources. The {open_quotes}integrated{close_quotes} software package of the BME-ECN module in the Neutron Metrology File NNW-90 is a user-friendly tool to process the library. Data for a comparison of calculated and experimental reaction rates in well defined neutron fields are also given.

• OSTI ID: 62101
• Report Number(s): CONF-940507-Vol.2; TRN: 95:002916-0030
• Resource Relation: Conference: International conference on nuclear data for science and technology: nuclear data for the twenty-first century, Gatlinburg, TN (United States), 9-13 May 1994; Other Information: PBD: 1994; Related Information: Is Part Of Proceedings of the international conference nuclear data for science and technology. Volume 2; Dickens, J.K. [ed.]; PB: 571 p.
• Country of Publication: United States
• Language: English

Related Subjects

66 PHYSICS
56 BIOLOGY AND MEDICINE
APPLIED STUDIES
99 MATHEMATICS
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
NUCLEAR DATA COLLECTIONS
EVALUATION
CROSS SECTIONS
DOSIMETRY