Published 1977 | Version v1
Report Metadata-only

Selection of fission product monitors for the determination of burnup for fast reactor fuels

Creators

  • 1. Allied Chemical Corp., Idaho Falls, ID

Description

The criteria for the selection of fission monitors for the determination of nuclear fuel burnup are reviewed. A system of comparing fission yields to aid in the selection of the most promising fission monitor is presented. Based on this review, it is apparent that no single nuclide will serve as a universal fission monitor, and that different monitors are preferred for different fuel types. For FBR plutonium fuels, the use of 143Nd as a fission monitor appears preferred compared to other neodymium isotopes

Additional details

Publishing Information

Imprint Title
Dosimetry methods for fuels, cladding, and structural materials
Journal Page Range
p. 313-320.
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
10441870
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; FBR TYPE REACTORS; FISSION PRODUCTS; FISSION YIELD; MEASURING METHODS; SOLID FUELS
Descriptors DEC
BREEDER REACTORS; ENERGY SOURCES; EPITHERMAL REACTORS; FAST REACTORS; FUELS; ISOTOPES; NUCLEAR FUELS; NUCLEAR REACTION YIELD; RADIOACTIVE MATERIALS; REACTOR MATERIALS; REACTORS