There is a newer version of the record available.

Published August 2004 | Version v1
Report Metadata-only

Analysis of Superphenix and Phenix neutron physics experiments with the ERANOS code and data system

Creators

  • 1. Commissariat a l'Energie Atomique (CEA), Saint-Paul-lez-Durance (France)

Description

The neutron physics commissioning tests for Super-Phenix and some tests in Phenix have been re-evaluated using the recent ERANOS-1.2 code system and the ERALIB1 adjusted nuclear data library based on the JEF-2.2 evaluated data file. Compared to the older code and data system, agreement with experiment excellent and is obtained without the need to apply numerous corrections due to method biases and data poor accuracy. (author)

Part of:
Operational and decommissioning experience with fast reactors. Proceedings of a technical meeting

Additional details

Identifiers

URL
http://www-pub.iaea.org/MTCD/publications/PDF/te_1405_web.pdf;

Publishing Information

ISBN
92-0-107804-8
Imprint Title
Operational and decommissioning experience with fast reactors. Proceedings of a technical meeting
Imprint Pagination
271 p.
Journal Page Range
p. 231-240
ISSN
1011-4289
Report number
IAEA-TECDOC--1405

Conference

Title
Technical meeting on operational and decommissioning experience with fast reactors
Dates
11-15 Mar 2004
Place
Cadarache (France)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
36031894
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
ACCURACY; COMPARATIVE EVALUATIONS; E CODES; EXPERIMENTAL DATA; GROUP CONSTANTS; MESH GENERATION; MULTIGROUP THEORY; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT THEORY; NUCLEAR DATA COLLECTIONS; PERTURBATION THEORY; PHENIX REACTOR; SUPER PHENIX REACTOR; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; VALIDATION
Descriptors DEC
BREEDER REACTORS; COMPUTER CODES; CROSS SECTIONS; DATA; DIFFERENTIAL EQUATIONS; DIFFUSION EQUATIONS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EQUATIONS; EVALUATION; FAST REACTORS; FBR TYPE REACTORS; INFORMATION; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; NEUTRON TRANSPORT THEORY; NUMERICAL DATA; PARTIAL DIFFERENTIAL EQUATIONS; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS; TESTING; TRANSPORT THEORY
Proposed descriptors and Free-text terms
collision probability method

Optional Information

Notes
9 refs, 7 tabs, 6 figs