Development and Validation of VVER-1000 Thermohydraulic Computer Model for TRACE Computer Code
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Keywords

TRACE, nuclear power plant, thermohydraulic analysis, thermohydraulic model, validation

How to Cite

Yanovskii, S., Zhabin, O., Vorobyov, Y., & Vyshemirskii, M. (2017). Development and Validation of VVER-1000 Thermohydraulic Computer Model for TRACE Computer Code. Nuclear and Radiation Safety, (1(73). https://doi.org/10.32918/nrs.2017.1(73).07

Abstract

The basic features of the development process, results of validation and their analysis are presented in the paper. VVER 1000/V-320 thermohydraulic model for TRACE computer code was developed. Validation calculation with this model was performed to confirm that this model is capable of simulating VVER 1000/V-320 nuclear power plant response during transients and accidents.

At the initial step of TRACE thermohydraulic model validation for VVER 1000/V-320, the initial and boundary conditions corresponding to the transient being evaluated were incorporated into the model and preliminary calculation was performed. The calculation results were compared with plant instrumentation data.

The following representative transients for which detailed plant instrumentation records are available were selected for validation calculation is “Rivne NPP (RNPP) Unit 3 pressurizer pilot operated relief valve (PORV) stuck in open position during scheduled tests”. An experience that has been obtained, expanded opportunities of the SSTC NRS to use modern codes in the scientific and technical support of NRC.

https://doi.org/10.32918/nrs.2017.1(73).07
ARTICLE PDF

References

1. TRACE V5.840 USER’S MANUAL. Vol. 1: Input Specification. Division of Safety Analysis Office of Nuclear Regulatory Research. U. S. Nuclear Regulatory Commission Washington, DC 20555-0001, 894 p.

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4. Report on the Investigation of RNPP Operational Events: Failure to Close Main Safety Valve PRZ PORV YP21S01 during Scheduled Checking of Operation by Real Pressure Increase in the Primary System before Startup of Unit 3 after Scheduled Outage due to Stacking of YP21S04 Valve in Spool after its Opening [Otchiot o rassledovanii narusheniia v rabote RAES: Nezakrytiie galvnogo predokhranitelnogo klapana IPU KD YP21S01 vo vremia planovoi proverki rabotosposobnosti realnym povysheniiem davleniia v pervom konture pered puskom energobloka No. 3 posle PPR iz-za podklinivaniia v sedle zolotnika impulsnogo klapana YP21S04 posle iego otkrytiia], RNPP, Kuznetsovsk,2009, 56 p. (Otchiot No. 3 ROV-P07-002-09-09D). (Rus)