Published January 1989
| Version v1
Journal article
Mass spectrometric measuring burnup of nuclear fuel
Creators
- 1. Academia Sinica, Beijing, BJ (China). Inst. of Atomic Energy
Description
The mass spectrometric determination of burnup in the reactor fuel is presented. The accuracies of results obtained by amounts of 236U growth, 235U decrease and indictor (148Nd) are 1.6-4.0%. The axial distributions of α5 and burnup (%) in irradiated fuel are demonstrated
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 23
- Journal Issue
- 1
- Series
- At. Energy Sci. Technol.
- Journal Page Range
- 44-49
- ISSN
- 1000-6931
- CODEN
- YKJIE
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 21042239
- Subject category
- S37: INORGANIC, ORGANIC, PHYSICAL AND ANALYTICAL CHEMISTRY;
- Descriptors DEI
- BURNUP; CORRECTIONS; DISTRIBUTION; ERRORS; FUEL ELEMENTS; ISOTOPE RATIO; MASS SPECTROSCOPY; MATHEMATICS; NEODYMIUM 148; URANIUM 235; URANIUM 236
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; EVEN-EVEN NUCLEI; EVEN-ODD NUCLEI; HEAVY NUCLEI; INTERMEDIATE MASS NUCLEI; INTERNAL CONVERSION RADIOISOTO; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MINUTES LIVING RADIOISOTOPES; NEODYMIUM ISOTOPES; NUCLEI; RADIOISOTOPES; RARE EARTH NUCLEI; REACTOR COMPONENTS; SPECTROSCOPY; SPONTANEOUS FISSION RADIOISOTO; STABLE ISOTOPES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES