Influence of Modelling Options in RELAP5SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity

المؤلفون المشاركون

Špalj, Srđan
Glaser, Bruno
Šadek, Siniša

المصدر

Science and Technology of Nuclear Installations

العدد

المجلد 2010، العدد 2010 (31 ديسمبر/كانون الأول 2010)، ص ص. 1-11، 11ص.

الناشر

Hindawi Publishing Corporation

تاريخ النشر

2009-11-22

دولة النشر

مصر

عدد الصفحات

11

التخصصات الرئيسية

العلوم الهندسية و تكنولوجيا المعلومات

الملخص EN

RELAP5/SCDAPSIM and MAAP4 are two widely used severe accident computer codes for the integral analysis of the core and the reactor pressure vessel behaviour following the core degradation.

The objective of the paper is the comparison of code results obtained by application of different modelling options and the evaluation of influence of thermal hydraulic behaviour of the plant on core damage progression.

The analysed transient was postulated station blackout in NPP Krško with a leakage from reactor coolant pump seals.

Two groups of calculations were performed where each group had a different break area and, thus, a different leakage rate.

Analyses have shown that MAAP4 results were more sensitive to varying thermal hydraulic conditions in the primary system.

User-defined parameters had to be carefully selected when the MAAP4 model was developed, in contrast to the RELAP5/SCDAPSIM model where those parameters did not have any significant impact on final results.

نمط استشهاد جمعية علماء النفس الأمريكية (APA)

Šadek, Siniša& Špalj, Srđan& Glaser, Bruno. 2009. Influence of Modelling Options in RELAP5SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity. Science and Technology of Nuclear Installations،Vol. 2010, no. 2010, pp.1-11.
https://search.emarefa.net/detail/BIM-450904

نمط استشهاد الجمعية الأمريكية للغات الحديثة (MLA)

Šadek, Siniša…[et al.]. Influence of Modelling Options in RELAP5SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity. Science and Technology of Nuclear Installations No. 2010 (2010), pp.1-11.
https://search.emarefa.net/detail/BIM-450904

نمط استشهاد الجمعية الطبية الأمريكية (AMA)

Šadek, Siniša& Špalj, Srđan& Glaser, Bruno. Influence of Modelling Options in RELAP5SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity. Science and Technology of Nuclear Installations. 2009. Vol. 2010, no. 2010, pp.1-11.
https://search.emarefa.net/detail/BIM-450904

نوع البيانات

مقالات

لغة النص

الإنجليزية

الملاحظات

Includes bibliographical references

رقم السجل

BIM-450904