Pressure-vessel-damage fluence reduction by low-leakage fuel management. [PWR]
As a result of neutron-induced radiation damage to the pressure vessel and of an increased concern that in a PWR transient the pressure vessel may be subjected to pressurized thermal shock (PTS), detailed analyses have been undertaken to determine the levels of neutron fluence accumulation at the pressure vessels of selected PWR's. In addition, various methods intended to limit vessel damage by reducing the vessel fluence have been investigated. This paper presents results of the fluence analysis and the evaluation of the low-leakage fuel management fluence reduction method. The calculations were performed with DOT-3.5 in an octant of the core/shield/vessel configuration using a 120 x 43 (r, theta) mesh structure.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA); Nuclear Regulatory Commission, Washington, DC (USA)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5756784
- Report Number(s):
- BNL-NUREG-33297; CONF-831047-72; ON: DE83015581
- Country of Publication:
- United States
- Language:
- English
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ALLOYS
CONTAINERS
DAMAGE
FUEL MANAGEMENT
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
NEUTRON FLUX
PHYSICAL RADIATION EFFECTS
PRESSURE VESSELS
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RADIATION EFFECTS
RADIATION FLUX
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REACTOR SAFETY
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STEELS
STRESSES
THERMAL STRESSES
TRANSIENTS
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