Published 1976 | Version v1
Book

Quality control tests for high-temperature gas-cooled reactor recycle fuel

  • 1. Oak Ridge National Lab., Tenn. (USA)

Description

Inspection of recycle fuel for HTGRs involves a large number of operations which, because of the high radiation level associated with the presence of 232U, must be performed in shielded (5cm of lead) glove boxes containing automated sample-handling and analysis equipment. Equipment for obtaining representative fuel particle samples and for pneumatically transferring particles and fuel rods through long tubes has been developed. Schemes for cross-checking inspection data were devised and shown to be useful for determining the accuracy and precision of several analytical techniques, as well as for detecting occasional errors in analytical data. The density of the particle buffer coating layer was shown to increase significantly during deposition of the overlying coating layer. A method was developed for determining the final buffer density to an accuracy of about 0.05g/cm3 while not requiring sampling at the buffer stage of the coating operation. Methods using high-pressure mercury pycnometry were developed for measuring both the amount of open porosity and the geometric density of low-temperature isotropic (LTI) coatings. With this technique the LTI density can be measured with a precision of about 0.01g/cm3. A 15000C gaseous chlorine leach technique was shown to be useful for measuring defective particle fractions for both loose particles and particles bonded into fuel rods. An automated particle size analyser suitable for glove-box operation was developed with the capability of measuring particles at the rate of 1500/min. Techniques for measuring particle shape and strength were also developed and demonstrated to be useful. (author)

Additional details

Publishing Information

Publisher
IAEA.
Imprint Place
Vienna
ISBN
92-0-050276-8
Imprint Title
Nuclear fuel quality assurance
Series
Proceedings series.
Journal Page Range
p. 425-447.

Conference

Title
Seminar on nuclear fuel quality assurance.
Dates
24 - 27 May 1976.
Place
Oslo, Norway.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
9376544
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COATED FUEL PARTICLES; DENSITY; GLOVEBOXES; HTGR TYPE REACTORS; INSPECTION; LABORATORY EQUIPMENT; MEASURING METHODS; NUCLEAR FUELS; QUALITY CONTROL; SAMPLING; SHIELDING; TESTING
Descriptors DEC
CONTROL; ENERGY SOURCES; FUEL PARTICLES; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; PHYSICAL PROPERTIES; REACTOR MATERIALS; REACTORS

Optional Information

Secondary number(s)
IAEA-SR--7/3.