A Comparison of Two Versions of a Proposed Test Reactor Using the MCNP Neutronics Code
| Autor: | Salim N. Jahshan, William K. Terry |
|---|---|
| Rok vydání: | 1995 |
| Předmět: |
Nuclear and High Energy Physics
Neutron transport 020209 energy Nuclear engineering Monte Carlo method 02 engineering and technology Nuclear reactor Condensed Matter Physics Pressure vessel law.invention Coolant 020303 mechanical engineering & transports 0203 mechanical engineering Nuclear Energy and Engineering Neutron flux law 0202 electrical engineering electronic engineering information engineering Code (cryptography) Environmental science Research reactor Nuclear chemistry |
| Zdroj: | Nuclear Technology. 110:93-105 |
| ISSN: | 1943-7471 0029-5450 |
| Popis: | The Broad-Application Test Reactor has been proposed for testing and isotope production missions in the early twenty-first century. Two conceptual designs, both employing metal plate fuel, light water coolant and a heavy water primary or secondary reflector region, survived an initial screening process. The Monte Carlo neutronics code (MCNP) was used to select one of these designs for future development. For each design, alternative fuel and pressure vessel materials were considered, and a preferred material was identified for each of the candidate designs. The design judged superior contains seven test regions, each surrounded by Zircaloy fuel annuli and enclosed by its own separate Zircaloy pressure boundary tube. |
| Databáze: | OpenAIRE |
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