Mitigation of an anticipated transient without scram event in a simplified boiling water reactor by the insertion of fine-motion control rods

Journal Article · Wed Nov 01 00:00:00 EST 1995 · Nuclear Technology

OSTI ID:163187

Khan, H J; Cheng, H S; Rohatgi, U S ^[1]

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1. Brookhaven National Lab., Upton, NY (United States)

Analysis has been performed for an anticipated transient without scram (ATWS) event in a simplified boiling water reactor. Loss of feedwater heating initiated this ATWS, which was mitigated by the insertion of fine-motion control rods. Calculations with RAMONA-4B code show that reactivity insertion, through increase in subcooling to the core, results in a rise in the core power to a new equilibrium condition. Insertion of fine-motion control rods from the bottom of the core is found to shift the peak of the axial power distribution to the upper part of the core until eventual shutdown of the reactor occurs.

• OSTI ID: 163187
• Journal Information: Nuclear Technology, Vol. 112, Issue 2; Other Information: PBD: Nov 1995
• Country of Publication: United States
• Language: English

Related Subjects

22 NUCLEAR REACTOR TECHNOLOGY
21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
ATWS
REGULATING RODS
MITIGATION
POSITIONING
R CODES
COMPUTERIZED SIMULATION
PERFORMANCE