Fast Neutron Fluence Calculation of BWR Pressure Vessel Internals
Conference
·
OSTI ID:786237
In recent years, cracks were found in some boiling water reactor (BWR) pressure vessel internals. This study is to help identify locations of possible failures due to the irradiation of fast neutrons at the BWR plant in Taiwan. This study shows that with proper geometric modeling, a nodal version of the three-dimensional discrete ordinates code TORT can be used to obtain quite accurate results in BWR fast neutron fluence calculations in reasonable computing time.
- Research Organization:
- National Tsing Hua University, Hsinchu (TW)
- Sponsoring Organization:
- none (US)
- OSTI ID:
- 786237
- Report Number(s):
- none; ISSN 0003-018X; CODEN TANSAO; ISSN 0003-018X; CODEN TANSAO
- Country of Publication:
- United States
- Language:
- English
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