Published January 1, 2007 | Version v1
Miscellaneous

Simultaneous nuclear data target accuracy study for innovative fast reactors

  • 1. CEA Cadarache (France)
  • 2. Idaho National Laboratory, Idaho Falls, ID (United States)
  • 3. Argonne National Laboratory (United States). Nuclear Engineering Division

Description

The present paper summarizes the major outcomes of a study conducted within a Nuclear Energy Agency Working Party on Evaluation Cooperation (NEA WPEC) initiative aiming to investigate data needs for future innovative nuclear systems, to quantify them and to propose a strategy to meet them. Within the NEA WPEC Subgroup 26 an uncertainty assessment has been carried out using covariance data recently processed by joint efforts of several US and European Labs. In general, the uncertainty analysis shows that for the wide selection of fast reactor concepts considered, the present integral parameters uncertainties resulting from the assumed uncertainties on nuclear data are probably acceptable in the early phases of design feasibility studies. However, in the successive phase of preliminary conceptual designs and in later design phases of selected reactor and fuel cycle concepts, there will be the need for improved data and methods, in order to reduce margins, both for economic and safety reasons. It is then important to define as soon as possible priority issues, i.e. which are the nuclear data (isotope, reaction type, energy range) that need improvement, in order to quantify target accuracies and to select a strategy to meet the requirements needed (e.g. by some selected new differential measurements and by the use of integral experiments). In this context one should account for the wide range of high accuracy integral experiments already performed and available in national or, better, international data basis, in order to indicate new integral experiments that will be needed to account for new requirements due to innovative design features, and to provide the necessary full integral data base to be used for validation of the design simulation tools.

Availability note (English)

Available from Argonne National Laboratory (US)

Additional details

Publishing Information

Publisher
Proc., pp. 113-117
Imprint Pagination
vp.
Report number
ANL/NE/CP--60288

Conference

Title
NEMEA-4 Workshop
Dates
16-18 Oct 2007
Place
Prague (Czech Republic)

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
41105117
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
ACCURACY; DATA; DESIGN; ENERGY RANGE; FAST REACTORS; FEASIBILITY STUDIES; FUEL CYCLE; REACTORS; TARGETS
Descriptors DEC
EPITHERMAL REACTORS; INFORMATION; REACTORS

Optional Information

Contract/Grant/Project number
AC02-06CH11357
Funding organization
USDOE Office of Science (United States)