Estimating the thermal neutron absorption cross section of nuclear graphite

Journal Article · Thu Jan 01 04:00:00 EST 1981 · Annu. Book ASTM Stand.; (United States)

OSTI ID:5543859

Three methods for estimating the thermal neutron absorption cross section of nuclear graphite are, in order of increasing reliability: (1) boron and ash, based on boron and ash content only; (2) common impurities, based on the concentrations of common impurities most likely to be present; and (3) delta-in-hours (DIH) purity, based on a measure of the difference in reactivity between standard graphite and test graphite bars. Facilities for DIH test are no longer in existence. These methods apply to graphites to be used for moderator or reflector components of nuclear reactors and subcritical test reactors and for thermal columns. Excluded from these methods are graphites containing fissionable materials for use as fuel or driver elements and graphites containing materials having high neutron absorption cross sections for use as reactor control or safety devices. (JMT)

• OSTI ID: 5543859
• Journal Information: Annu. Book ASTM Stand.; (United States), Journal Name: Annu. Book ASTM Stand.; (United States) Vol. 45; ISSN ABASC
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
654003* -- Radiation & Shielding Physics-- Neutron Interactions with Matter
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ABSORPTION
ABSORPTION HEAT
ASHES
BARYONS
BORON
CARBON
CROSS SECTIONS
ELEMENTAL MINERALS
ELEMENTARY PARTICLES
ELEMENTS
ENERGY
ENTHALPY
FERMIONS
GRAPHITE
HADRONS
HEAT
IMPURITIES
INDUSTRY
MATERIALS
MINERALS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON ABSORBERS
NEUTRON REFLECTORS
NEUTRON TRANSPORT
NEUTRONS
NONMETALS
NUCLEAR INDUSTRY
NUCLEONS
PHYSICAL PROPERTIES
RADIATION TRANSPORT
REACTOR MATERIALS
RESIDUES
SEMIMETALS
STANDARDS
THERMAL NEUTRONS
THERMODYNAMIC PROPERTIES