Measurements of delayed neutron emission from Np-237, Am-241, and Am-243

Technical Report · Fri Dec 01 04:00:00 EST 1995

DOI:https://doi.org/10.2172/162197· OSTI ID:162197

Saleh, H H; Parish, T A ^[1]; Raman, S ^[2]

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1. Texas A&M Univ., College Station, TX (United States)
2. Oak Ridge National Lab., TN (United States)

Isotopes of transuranic elements are produced as a result of successive radiative capture reactions in the fuel of a nuclear reactor. Typically, these transuranic isotopes decay through long chains, have long half lives and dominate the long term toxicity of the spent reactor fuel. One of the options for waste management is to remove the transuranic from spent fuel by chemical processing, to load them into new special fuel elements, and to transmute them by neutron induced fission into shorter-lived fission fragments. Previous studies have shown the feasibility of actinide transmutation in either Light Water Reactors or Liquid Metal Fast Reactors. Due to the anticipated high transuranic loadings in the fuel of actinide burner reactors, the neutronic properties of the transuranic isotopes will have a significant effect on the operational and safety characteristics of such reactors. Experiments to determine delayed neutron group yields and decay constants for Np-237, Am-241, and Am-243 have been designed and carried out. The experiments were conducted at Texas A&M University TRIGA reactor using a very fast pneumatic transfer system.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States); Japan Atomic Energy Research Inst., Tokyo (Japan)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 162197
• Report Number(s): CONF-950601--28; ON: DE96003020
• Country of Publication: United States
• Language: English

Related Subjects

66 PHYSICS
AMERICIUM 241
AMERICIUM 243
DELAYED NEUTRONS
EXPERIMENTAL DATA
FISSION FRAGMENTS
NEPTUNIUM 237
NEUTRON EMISSION
NUCLEAR DATA COLLECTIONS