2012 Help me understand this report
Verification and validation of the PLTEMP/ANL code for thermal hydraulic analysis of experimental and test reactors
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“…The thermal hydraulic safety analysis of the MNSR reactor, a very similar reactor to the SLOWPOKE-2, outlined in [11] was used as a general reference for the analysis of JM-1. The MNSR analysis was performed with PLTEMP/ANL V4.1 code, using a one-pin (average or peak power pin) equivalent unit cell model to simulate the reactor core configurations.…”
Section: Heu Core Thermal Hydraulic Modelmentioning
confidence: 99%
“…The thermal hydraulic safety analysis of the MNSR reactor, a very similar reactor to the SLOWPOKE-2, outlined in [11] was used as a general reference for the analysis of JM-1. The MNSR analysis was performed with PLTEMP/ANL V4.1 code, using a one-pin (average or peak power pin) equivalent unit cell model to simulate the reactor core configurations.…”
Section: Heu Core Thermal Hydraulic Modelmentioning
confidence: 99%
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