Published April 1988 | Version v1
Report

Thermal-hydraulic considerations in nuclear power plant license renewal

Creators

  • 1. Nuclear Regulatory Commission, Washington, DC (USA)

Description

A major issue looming in the future for both the NRC and the regulated industry is the matter of license renewal. This is the renewal of licenses beyond the current 40 year plant life (not to be confused with license extension involving moving the start date of the 40 year life from the CP issuance to the OL issuance). While it is too early to speculate as to what shape the license renewal policy and regulations will take, it is not too early to conclude that each licensee will have to demonstrate why its plant can operate safely beyond 40 years. Exactly how this demonstration must be made is the subject of an extensive policy development program and rulemaking process at the NRC. There are certain areas of thermal hydraulic analysis that may be important to license renewal. These are 1) Pressurized Thermal Shock to Pressure Vessels, 2) Management of Severe Accidents, 3) Plant Simulators, and 4) Transient Histories. Each of these is briefly discussed

Additional details

Publishing Information

Imprint Title
Proceedings: Fifth International RETRAN conference
Journal Page Range
p. 5.1-5.4.
Report number
EPRI-NP--5781-SR

Conference

Title
5. international RETRAN meeting.
Dates
9-11 Nov 1987.
Place
Boston, MA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
20030703
Subject category
S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; R CODES; REACTOR CORE DISRUPTION; REACTOR SAFETY; SYSTEMS ANALYSIS; TEMPERATURE GRADIENTS; THERMODYNAMICS; TRANSIENTS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS