Analysis of the damage domains of sbo sequences with rcp passive thermal shutdown

The integrated Safety Assessment (ISA) methodology, developed by the Spanish Nuclear Safety Council (CSN), has been applied to a thermal-hydraulic analysis of PWR Station Blackout (SBO) sequences in the context of the IDPSA (Integrated Deterministic-Probabilistic Safety Assessment) network objectives. The ISA methodology allows obtaining the damage domain (the region of the uncertain parameters space where the damage limit is exceeded) for each sequence of interest as a function of the operator actuations times. Given a particular safety limit or damage limit, several data of every sequence are necessary in order to obtain the exceedance frequency of that limit. In this application these data are obtained from the results of the simulations performed with MAAP code transients inside each damage domain and the time-density probability distributions of the manual actions. Damage limits that have been taken into account within this analysis are: local cladding damage (PCT>1477 K); local fuel melting (T>2499 K); fuel relocation in lower plenum and vessel failure. Therefore, to every one of these damage variables corresponds a different damage domain. The operation of the new passive thermal shutdown seals developed by several companies since Fukushima accident is considered in the paper. The results show the capability and necessity of the ISA methodology, or similar, in order to obtain accurate results that take into account time uncertainties.

Development of a PWR-W and an AP1000® containment building 3D model with a CFD code for Best-Estimate Thermal-Hydraulic Analysis

The simulation of design basis accidents in a containment building is usually conducted with a lumped parameter model. The codes normally used by Westinghouse Electric Company (WEC) for that license analysis are WGOTHIC or COCO, which are suitable to provide an adequate estimation of the overall peak temperature and pressure of the containment. However, for the detailed study of the thermal-hydraulic behavior in every room and compartment of the containment building, it could be more convenient to model the containment with a more detailed 3D representation of the geometry of the whole building. The main objective of this project is to obtain a standard PWR Westinghouse as well as an AP1000® containment model for a CFD code to analyze the thermal-hydraulic detailed behavior during a design basis accident. In this paper the development and testing of both containment models is presented.

Trusted Tiny Things : Making Devices in Smart Cities More Transparent

Postprint

Phoenix Memorial Project 3/5

Ford Nuclear Reactor UM Nuclear engineering students attend class at the Ford Nuclear Reactor. Charles Ricker, instructor in Nuclear Engineering, Dept. of Electrical Engineering, and Reactor Operator, describes the oepration of the control panel. Michigan Memorial Phoenix project started in 1948 to find peacetime applications for atomic energy.

Phoenix Memorial Project 3/5

Ford Nuclear Reactor UM Nuclear engineering students attend class at the Ford Nuclear Reactor. Charles Ricker, instructor in Nuclear Engineering, Dept. of Electrical Engineering, and Reactor Operator, describes the oepration of the control panel. Michigan Memorial Phoenix project started in 1948 to find peacetime applications for atomic energy.

A handbook of acronyms and initialisms /

"NUREG-0544."

Reactor hot channel factors and burnout : a literature search /

"November 1962."

Factors affecting the use of CaF2 : Mn thermoluminescent dosimeters for low-level environmental radiation monitoring /

Mode of access: Internet.

Criticality studies : a literature search /

"August 1959."

Informal listing of bibliographies of atomic energy literature : bibliographies issued or in progress during the period.

TID-3717 cover misprinted as Feb./Mar 1963, should be Apr./May 1963.

Bibliographies of atomic energy literature.

"Issued or in progress during the period ..."

Criticality : a bibliography of unclassified literature /

Includes indexes.

The determination of uranium isotope abundances and reactor fuel burnup by mass spectrometry /

April 17, 1963--page 11.

An empirical interpretation of annuli critical mass data /

"U.S. Atomic Energy Commission Contract AT(29-1)-1106."

Criticality measurements performed in situ /

"Date Distributed: Nov 15 1961."