English (United Kingdom)

https://curated-unify.zendy.io/wp-json/zendy-region/v1/featured_content/oa?rat=en

https://curated-unify.zendy.io/wp-json/zendy-region/v1/highlighted_journal/

Global: Zendy Plus annual

Presents the access of premium content as premium feature

Premium Content

Presents the keyphrase highlighting as premium feature

Keyphrase Highlighting

Presents the summarisation as premium feature

Summarisation

Insights

Presents the pdf analysis as premium feature

PDF Analysis

Presents the zaia usage as premium feature

ZAIA

Global: Zendy Tools annual

Global: Zendy Free Plan

Global: Zendy Tools monthly

Global: Zendy Plus monthly

This paper presents the results of the analysis of the Unprotected Loss of Flow (ULOF) experiment SHRT-45R performed in the EBR-IIfast reactor. These experiments are being analyzed in the scope of a benchmark exercise coordinated by the IAEA. The SHRT-45Rbenchmark contains a neutronic and a thermal-hydraulic part and results are presented for both. Neutronic calculations are performed withthe ERANOS2.0 code in combination with various sets of nuclear data. The thermal-hydraulic evaluation is done with RELAP5-3D. Theresults are that the major neutronic parameters are well predicted with error margins on the order of 1%. The thermal-hydraulic results areless favourable: a consistent overestimation of the outlet temperature occurs in combination with erroneous flow distribution. Observeddifferences with measured data cannot be explained easily. The work presented in this paper was undertaken to investigate and validate theeffectiveness of the calculational tools and data that are commonly used in our lab for the design and analysis of liquid metal cooled fastreactors

Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment with ERANOS and RELAP