PROGRAM FOR THE DEVELOPMENT OF PLUTONIUM RECYCLE FOR USE IN LIGHT WATER MODERATED REACTORS. Quarterly Progress Report, January 1-March 31, 1963
The program fuel element was exposed to a burnup of 485 Mwd/t, which brings the total to 2334 Mwd/t, in the VBWR. Chemical and mass-spectrographic assays were completed on six radial samples and the pellet average sample extracted from a rod at an estimated burnup of 2000 Mwd/t. Cerium and cesium analyses indicated burnup of about 1880 Mwd/t. Autoradiographic and metallographic examination of the polished surface of the rod showed that the micro-segregation of the PuO/sub 2/ observed in the fabricated fuel was still present. Thermal average cross sections for all of the isotopes contained in the project fuel were computed by the THERMOS code. The epithermal cross sections and the fast-to-slow flux ratio were obtained from a MUFT-type calculation. (M.C.G.)
- Research Organization:
- General Electric Co. Vallecitos Atomic Lab., Pleasanton, Calif.
- DOE Contract Number:
- AT(04-3)-189
- NSA Number:
- NSA-17-028431
- OSTI ID:
- 4695329
- Report Number(s):
- GEAP-4216; EURAEC-633
- Resource Relation:
- Other Information: Work performed under United States-Euratom Joint Research and Development Program. Orig. Receipt Date: 31-DEC-63
- Country of Publication:
- United States
- Language:
- English
Similar Records
PROGRAM FOR THE DEVELOPMENT OF PLUTONIUM RECYCLE FOR USE IN LIGHT WATER MODERATED REACTORS. Quarterly Report No. 10, July 1-September 30, 1963
PROGRAM FOR THE DEVELOPMENT OF PLUTONIUM RECYCLE FOR USE IN LIGHT-WATER- MODERATED REACTORS. Eleventh Quarterly Report, October 1-December 31, 1963
Related Subjects
BREEDING
BURNUP
CERIUM
CESIUM
CROSS SECTIONS
EPITHERMAL NEUTRONS
FUEL ELEMENTS
ISOTOPES
MASS SPECTROMETERS
METALLOGRAPHY
PELLETS
PLUTONIUM
PLUTONIUM OXIDES
PROGRAMMING
QUALITATIVE ANALYSIS
RADIOCHEMISTRY
REACTORS
RESEARCH REACTORS
SPECTRA
SURFACES
THERMAL NEUTRONS
USES
VBWR
WATER MODERATOR