Published May 23, 2001 | Version v1
Report

The capability of internal assessment of uncertainty

  • 1. Dipartimento di Ingegneria Meccanica, Nucleare e della Produzione, Universita di Pisa, Via Diotisalvi 2, 56100 PISA (Italy)
  • 2. ANPA, Via Vitaliano Brancati 44 00100 ROMA (Italy)

Description

The internal assessment of uncertainty is a desirable capability for thermalhydraulic system codes. This consists in the possibility of obtaining proper uncertainty bands each time a nuclear plant transient scenario is calculated. In the present paper, a methodology suitable for introducing such a capability into a system code is discussed. At the basis of the derivation of the CIAU (Code with - the capability of - Internat Assessment of Uncertainty) there is the UMAE (Uncertainty Methodology based on the Accuracy Extrapolation), previously proposed by University of Pisa, though other uncertainty methodologies can be used for the same purpose. The idea of the CIAU is the identification and the characterization of standard plant statuses and the association of uncertainty to each status. One hypercube and one time interval identify the plant status. 'Quantity' and 'Time' uncertainties are combined for each plant status. The recently released US NRC (Nuclear Regulatory Commission) Relap5/mod3.2 system code constitutes the CIAU. This is used for showing the applicability of the proposed method. In the present paper the derivation of the methodology is discussed and reference results of PWR (Pressurized Water Reactor) plant transients are shown bounded by the CIAU calculated uncertainty bands. (authors)

Part of:
Proceedings of the workshop on advanced thermal-hydraulic and neutronic codes: current and future applications

Additional details

Publishing Information

Imprint Title
Proceedings of the workshop on advanced thermal-hydraulic and neutronic codes: current and future applications
Imprint Pagination
723 p.
Journal Page Range
p. 634-656
Report number
NEA-CSNI-R--2001-2

Conference

Title
current and future applications
Acronym
Workshop on advanced thermal-hydraulic and neutronic codes
Dates
10-13 Apr 2000
Place
Barcelona (Spain)

INIS

Country of Publication
Nuclear Energy Agency of the OECD (NEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
39036600
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; EXTRAPOLATION; NUCLEAR POWER PLANTS; PWR TYPE REACTORS; STANDARDS; TRANSIENTS; US NRC
Descriptors DEC
ENRICHED URANIUM REACTORS; MATHEMATICAL SOLUTIONS; NATIONAL ORGANIZATIONS; NUCLEAR FACILITIES; NUMERICAL SOLUTION; POWER PLANTS; POWER REACTORS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
30 refs.