Calculation of fuel burn up and radioactive inventory in a CANDU reactor using WIMS-D4 code
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference6 articles.
1. Effect of new cross sections evaluations on criticality and neutron energy spectrum of a typical material test research reactor;Ahmad;Ann. Nucl. Energy,2004
2. Halsall, M.J., 1980. Summary of WIMSD4 input options. AEEW-M 1327.
3. Neutronics analysis of natural uranium fueled, light water cooled, heavy water moderated and graphite reflected nuclear reactors;Khan;Ann. Nucl. Energy.,2004
4. Power flattening in the fuel bundle of a CANDU reactor;Sahin;Nucl. Eng. Des.,2004
5. An assessment of thorium and spent LWR-fuel utilization potential in CANDU reactors;Sahin;Energy Convers. Manage.,2006
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