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Depletion codes

M. J. Bell, ORJGEN—The ORNL Isotope Generation and Depletion Code, ORNL-4628, Oak Ridge National Laboratory, Oak Ridge, Term., 1973. [Pg.205]

Bell, M. J., "ORIGEN - The ORNL Isotope Generation and Depletion Code," Oak Ridge National Laboratory Report ORNL-4628 (1972). [Pg.126]

Bl. Barry, R. F. LEOPARD-A Spectrum Dependent Non-Spatial Depletion Code for the IBM-7094, Westinghouse Electric Corp., Report WCAP-3269-26, Sep. 1963. [Pg.153]

Bahr, W., et al. Experiences in the Treatment of Low- and Intermediate-Level Radioactive Wastes in the Nuclear Research Center, Karlsruhe, Management of Low- and Intermediate-Level Radioactive Wastes, International Atomic Energy Agency, Vienna, 1970. Bell, M. J. The ORNL Isotope Generation and Depletion Code (ORIGEN), Report ORNL-4628, May 1973. [Pg.624]

Currently the Branch is using the OREL Isot< Generation and Depletion Code to determine source terms for our shielding analyses. Shielding analyses are being... [Pg.400]

Non-Spatial Depletion Code for the IBM-7094," WCAP-, ". 3269-26, Westinghouse Electric Corporation (1963). J... [Pg.506]

RSIC Computer Code Collection, ORIGEN, CCC-217, "Isotope Generation and Depletion Code, Oak Ridge National Lab. [Pg.609]

W. A. WITTKOPF et al., NUUF-A Neutron Spectrum Generator, Few Group Constant Calculator and Fuel Depletion Code, BAW-10115 (Mar. 1976). [Pg.680]

Groff, A.G. ORIGEN2 - A Revised and Updated Version of the Oak Ridge Isotope Generation and Depletion Code, ORNL-5624,1980. [Pg.176]

Table III. 8 of Appendix III summarizes the ongoing and planned developments of the calculation technologies and data sets relevant for the SMR designs considered. The R D directions cover the neutronic codes and nuclear data, the thermal-hydraulic and safety analyses codes, the uncertainty analysis codes, the depletion codes, the fuel performance codes, and the databases of material properties. Table III. 8 of Appendix III summarizes the ongoing and planned developments of the calculation technologies and data sets relevant for the SMR designs considered. The R D directions cover the neutronic codes and nuclear data, the thermal-hydraulic and safety analyses codes, the uncertainty analysis codes, the depletion codes, the fuel performance codes, and the databases of material properties.
The prompt Doppler reactivity coefficient and the moderator temperature coefficient must remain negative over the entire fuel exposure. The prompt change was evaluated only at one other exposure in an attempt to provide some insight into exposure-dependent behavior. The 16-mm-diameter rod was evaluated at an exposure of 500 GWD/MT. Isotopic compositions were calculated using the ORIGEN2 isotopic generation and depletion code with appropriate... [Pg.76]

CEA and AREVA NC have developed and used a depletion code named CESAR for 30 years. This user-friendly industrial tool provides fast characterisations for all types of nuclear fuel (PWR / UOX or MOX or reprocess Uranium, BWR / UOX or MOX, MTR and SFR) and the wastes associated. CESAR can evaluate 100 heavy nuclides, 200 fission products and 150 activation products (with Helium and Tritium formation). It can also... [Pg.202]


See other pages where Depletion codes is mentioned: [Pg.21]    [Pg.606]    [Pg.100]    [Pg.27]    [Pg.44]    [Pg.203]    [Pg.203]    [Pg.41]   
See also in sourсe #XX -- [ Pg.161 ]




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