Published 2015 | Version v1
Book Metadata-only

Measurement of the neutron capture cross section of the fissile isotope 235U with the CERN nTOF Total Absorption Calorimeter and fission tagging based on micromegas detectors

Creators

Description

The future nuclear technologies require accurate nuclear data on neutron-induced capture cross sections and α ratios of fissile isotopes. The measurement of their cross section present several difficulties, most of them related to the larger fission γ-ray background competing with the weaker γ-ray cascades from the capture reactions used as signal. A specific setup was used for the measurement of 235U capture cross section at the CERN nTOF facility in 2012. The setup consists of a set of micromegas fission detectors surrounding the 235U samples all placed inside a segmented BaF2 Total Absorption Calorimeter. (Author)

Part of:
41st Annual Meeting of the Spanish Nuclear Society

Additional details

Identifiers

URL
https://www.sne.es/es/agenda/actividades-organizadas-por-la-sne/reunion-anual/reunion-anual-41;

Publishing Information

Publisher
Editorial Senda
Imprint Place
A Coruna (Spain)
Imprint Title
41st Annual Meeting of the Spanish Nuclear Society
Imprint Pagination
140 p.
Journal Page Range
6 p.

Conference

Title
41. Annual Meeting of the Spanish Nuclear Society
Dates
23-25 Sep 2015
Place
A Coruna (Spain)

INIS

Country of Publication
Spain
Country of Input or Organization
Spain
INIS RN
48010620
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
NUCLEAR INDUSTRY; NUCLEAR POWER PLANTS; RESEARCH PROGRAMS; SAFETY ANALYSIS
Descriptors DEC
INDUSTRY; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information