Published 1974 | Version v1
Report

Reliable core thermal design

Creators

  • 1. Commission of the European Communities, Brussels (Belgium)

Description

The hot spot analysis is no longer limited to the calculation of a simple safety factor against overtemperature, but is now integrated in the overall design philosophy. This paper describes the development of a probabilistic method of analysis and compares it with other advanced calculation methods. Feedbacks from the analysis act: - on the nominal temperature distribution in order to satisfy the maximum temperature limit and in the same time to optimize the coolant temperature for maximum plant efficiency, and - on the specifications of manufacturing tolerances and experimental investigations in order to identify and to reduce the most important design uncertainties. Moreover the computer codes SHOSPA and THEDRA are briefly discussed. Both codes deliver the zero hot spot probability as a function of the geometrical size assumed for a ''spot''. THEDRA delivers also the expected hot spot distribution. By means of THEDRA it is possible to evaluate the pins failure expectation if the distribution of pin failures versus operating temperature is known. (author)

Additional details

Publishing Information

Imprint Title
Principles of hot-channel factor calculations for fast reactors
Imprint Pagination
p. 1-20.
Report number
IAEA--166

Conference

Title
Panel meeting on principles of hot-channel factor calculations for LMFBR's.
Dates
22 Nov 1973.
Place
Karlsruhe, F.R. Germany.

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
6218575
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
HEAT TRANSFER; HOT CHANNEL; HOT SPOT FACTOR; HOT SPOTS; REACTOR CORES; S CODES; T CODES
Descriptors DEC
COMPUTER CODES; ENERGY TRANSFER; REACTOR COMPONENTS