Published November 2005 | Version v1
Journal article Metadata-only

Introduction to burn-up measurement method of nuclear fuel

Creators

  • 1. Tsinghua Univ., Beijing (China). Inst. of Nuclear and New Energy Technology

Description

The state about the burn-up measurement of the non-destructive analysis and destructive analysis has been introduced in this report. The development trends of the burn-up measurement on the multi-detectors spent fuel measurement system used by gamma spectroscopy and neutron detector are described. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Electronics and Detection Technology
Journal Volume
25
Journal Issue
6
Journal Page Range
p. 852-857
ISSN
0258-0934

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
37113439
Subject category
S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
Descriptors DEI
BURNUP; GAMMA SPECTROSCOPY; MEASURING METHODS; NEUTRON DETECTORS; NONDESTRUCTIVE ANALYSIS; SPENT FUELS
Descriptors DEC
CHEMICAL ANALYSIS; ENERGY SOURCES; FUELS; MATERIALS; MEASURING INSTRUMENTS; NUCLEAR FUELS; RADIATION DETECTORS; REACTOR MATERIALS; SPECTROSCOPY

Optional Information

Notes
4 figs., 40 refs.