CPB reviews the following: 1. The types of control rod misoperations that are assumed to occur. For a pres-surized water reactor (PWR), this may include one or more rods moving or dis-placed from normal or allowed control bank positions (such as dropped rods and rods left behind when inserting or withdrawing banks, or single rod withdrawal) and may include the automatic control system attempting to maintain full power. For a boiling water reactor (BWR) with current modes of control rod operation, limiting anomalies are reviewed under SRP Sections 15.4.1 and 15.4.2, and no additional areas are considered here. 2. Descriptions of.rod position, flux, pressure, and temperature indication sys-tems, and those actions initiated by these systems (e...
International audienceNuclear reactors exhibit excess reactivity at start-up to ensure continuous op...
Abnormal vibration has been observed on the central cruciform shaped control rod in the Open Pool Au...
A decrease in reactor coolant flow occurring while the plant is at power could result in a degradati...
The CPB evaluates the consequences of a control rod ejection accident in the area of physics. The re...
The events postulated are an instantaneous seizure of the rotor or break of the shaft of a reactor c...
A number of transients that may occur with moderate frequency cause 'either increased core flow...
Hypothetical transients and accidents are used in the design and safety analysis of light-water reac...
The PSB reviews reactor auxiliary cooling water systems (CWS) that are required for safe shutdown du...
For Mark I, II, and III- pressure-suppression type boiling water reactor (BWR) plant containments, t...
The transient that results from a postulated feedwater line break is sensitive to the break discharg...
During operation of nuclear power reactors reactivity initiated accidents (RIA) can occur, such as a...
The core reactivity and power distribution within the core of a pressurized water reactor (PWR) are ...
This paper examined the control rod drop-failure in nuclear power plants. Safety margin test was con...
The residual heat removal (RHR) system is used in conjunction with the main steam and feedwater syst...
The Interim Staff Guidance on burnup credit (ISG-8) for pressurized water reactor (PWR) spent nuclea...
International audienceNuclear reactors exhibit excess reactivity at start-up to ensure continuous op...
Abnormal vibration has been observed on the central cruciform shaped control rod in the Open Pool Au...
A decrease in reactor coolant flow occurring while the plant is at power could result in a degradati...
The CPB evaluates the consequences of a control rod ejection accident in the area of physics. The re...
The events postulated are an instantaneous seizure of the rotor or break of the shaft of a reactor c...
A number of transients that may occur with moderate frequency cause 'either increased core flow...
Hypothetical transients and accidents are used in the design and safety analysis of light-water reac...
The PSB reviews reactor auxiliary cooling water systems (CWS) that are required for safe shutdown du...
For Mark I, II, and III- pressure-suppression type boiling water reactor (BWR) plant containments, t...
The transient that results from a postulated feedwater line break is sensitive to the break discharg...
During operation of nuclear power reactors reactivity initiated accidents (RIA) can occur, such as a...
The core reactivity and power distribution within the core of a pressurized water reactor (PWR) are ...
This paper examined the control rod drop-failure in nuclear power plants. Safety margin test was con...
The residual heat removal (RHR) system is used in conjunction with the main steam and feedwater syst...
The Interim Staff Guidance on burnup credit (ISG-8) for pressurized water reactor (PWR) spent nuclea...
International audienceNuclear reactors exhibit excess reactivity at start-up to ensure continuous op...
Abnormal vibration has been observed on the central cruciform shaped control rod in the Open Pool Au...
A decrease in reactor coolant flow occurring while the plant is at power could result in a degradati...