Reactor physics and standards in the framework of European collaborations

Conference · Wed Jan 01 00:00:00 EST 1992 · Transactions of the American Nuclear Society; (United States)

OSTI ID:6683254

Conde, H ^[1]; Rowlands, J; Salvatores, M ^[2]; Sowerby, M ^[3]

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1. Uppsala Univ. (Sweden)
2. Commissariat a l'Energie Atomique, Saint-Paul-les-Durance (France)
3. United Kingdom Atomic Energy Authority, Oxfordshire (United Kingdom)

This paper discusses some aspects of the standardization of data within European collaborations on reactors. It is not always possible to use identical standards because national projects often have excellent reasons for not changing, e.g., back compatibility. In such cases, intercomparisons are made. Most recommended standards are based on Joint Evaluated File (JEF) Project evaluations. Because of the key role of integral measurements in the validation of recommended data, intercomparison of integral measurement techniques has also been an important activity. The JEF Project is a collaboration between the member countries of the Nuclear Energy Agency (NEA) Data Bank. The main aim of the project is to provide neutron cross-section libraries for thermal and fast reactor calculations. It has been agreed that the standards for cross-section measurements will be the ENDF/B-VI standards internationally accepted by the Organization for European Cooperation and Development/NEA and the International Atomic Energy Agency nuclear data committees. There are close links with the European Fusion File Project.

• OSTI ID: 6683254
• Report Number(s): CONF-921102-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 66; Conference: Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction: past, present, and future, Chicago, IL (United States), 15-20 Nov 1992; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
NUCLEAR DATA COLLECTIONS
STANDARDS
AFTER-HEAT REMOVAL
CROSS SECTIONS
DAMAGING NEUTRON FLUENCE
DELAYED NEUTRONS
IAEA
INTERNATIONAL COOPERATION
MEASURING METHODS
NEA
BARYONS
COOPERATION
ELEMENTARY PARTICLES
FERMIONS
FISSION NEUTRONS
HADRONS
INTERNATIONAL ORGANIZATIONS
NEUTRON FLUENCE
NEUTRONS
NUCLEONS
OECD
REMOVAL
220100* - Nuclear Reactor Technology- Theory & Calculation