Published 1977 | Version v1
Report

Review of fuel burnup techniques in U.S

Creators

  • 1. Babcock and Wilcox, Lynchburg, VA

Description

Measurement of fuel burnup and the development of methods for measurement of fuel burnup are performed at numerous industrial and government laboratories. Most of the burnup measurements are associated with fuel development and testing for fast, light water and gas cooled reactors. Development and evaluation of burnup methods are primarily centered in government laboratories. The development work is directed at fast reactor applications, but most of the methods being tested are likely to be useful for light water reactors also. Determination of fission yields from various actinide nuclides continues to be a major activity. Most burnup measurements use a combined heavy element-neodymium-148 method. High resolution gamma spectroscopy is used frequently, both for non-destructive scanning and destructive burnup analysis. Several spectrophotometric methods have been used. The most successful spectrophotometric determination is zirconium for gas cooled reactor fuel. Development work includes better separation techniques and evaluation of new monitors

Additional details

Publishing Information

Imprint Title
Dosimetry methods for fuels, cladding, and structural materials
Journal Page Range
p. 469-475.
Report number
NUREG/CP--0004(Vol.1)

Conference

Title
dosimetry methods for fuels, cladding and structural materials.
Acronym
2. ASTM-EURATOM symposium on reactor dosimetry
Dates
2 - 7 Oct 1977.
Place
Palo Alto, CA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
10441739
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; GAMMA SPECTROSCOPY; MEASURING METHODS; NUCLEAR FUELS; REVIEWS
Descriptors DEC
DOCUMENT TYPES; ENERGY SOURCES; FUELS; REACTOR MATERIALS; SPECTROSCOPY