Heavy Nuclide Cross Sections of Particular Interest to Thermal Reactor Operation: Conventions, Measurements and Preferred Values

Journal Article · Sat Aug 01 00:00:00 EDT 1959 · Nuclear Science and Engineering

OSTI ID:4221906

Stoughton, R. W. ^[1]; Halperin, J. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

The various conventions and definitions of thermal and resonance flux are discussed. Measurements of the thermal neutron cross sections, resonance integrals, and reactor cross sections of the following nuclides are critically reviewed: Th²³², Th²³³, Pa²³³, U²³³, U²³⁴, U²³⁵, U²³⁶, U²³⁸, U²³⁹, Np²³⁹, Pu²³⁹, Pu²⁴⁰, Pu²⁴¹, and Pu²⁴².

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-13-019636
• OSTI ID: 4221906
• Journal Information: Nuclear Science and Engineering, Journal Name: Nuclear Science and Engineering Vol. 6; ISSN 0029-5639
• Publisher: Taylor & Francis
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
CROSS SECTIONS
ENERGY RANGE
EV RANGE
NEPTUNIUM 239
NEUTRON FLUX
Nuclear Criticality Safety Program (NCSP)
PLUTONIUM 240
PLUTONIUM 241
PLUTONIUM 242
PROTACTINIUM 233
REACTORS
RESONANCE ESCAPE PROBABILITY
RESONANCE NEUTRONS
THERMAL NEUTRONS
THORIUM 232
THORIUM 233
URANIUM 233
URANIUM 234
URANIUM 235
URANIUM 236
URANIUM 238
URANIUM 239