Computational features of the MELT-III neutronics, thermal-hydraulics computer code system
Conference
·
OSTI ID:4069775
A multichannel, thermal-hydraulics, neutronic accident analysis program for simulating fast reactor behavior from a hypothetical accident inception to the start of core disassembly or to reactor shutdown is described. (JWR)
- Research Organization:
- Hanford Engineering Development Lab., Richland, Wash. (USA)
- NSA Number:
- NSA-33-022322
- OSTI ID:
- 4069775
- Report Number(s):
- HEDL-SA-9085; CONF-750607-41
- Resource Relation:
- Conference: American Nuclear Society meeting, New Orleans, Louisiana, USA, 8 Jun 1975; Other Information: Orig. Receipt Date: 30-JUN-76
- Country of Publication:
- United States
- Language:
- English
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