Published March 1977 | Version v1
Report Restricted

Additional methodology development for statistical evaluation of reactor safety analyses

Creators

Description

The project described is motivated by the desire for methods to quantify uncertainties and to identify conservatisms in nuclear power plant safety analysis. The report examines statistical methods useful for assessing the probability distribution of output response from complex nuclear computer codes, considers sensitivity analysis and several other topics, and also sets the path for using the developed methods for realistic assessment of the design basis accident

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A06/MF A01.

Files

Restricted

The record is publicly accessible, but files are restricted to users with access.

Additional details

Additional titles

Augmented title (English)
BWR; PWR

Publishing Information

Imprint Pagination
108 p.
Report number
EPRI-NP--483

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
9360459
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
ACCURACY; BWR TYPE REACTORS; COMPUTER CALCULATIONS; DESIGN BASIS ACCIDENTS; MATHEMATICAL MODELS; MATHEMATICS; NUCLEAR POWER PLANTS; PROBABILITY; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; STATISTICS
Descriptors DEC
ACCIDENTS; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; SAFETY; THERMAL POWER PLANTS; WATER COOLED REACTORS; WATER MODERATED REACTORS