DYNAMICAL METHOD APPLICATION ANALYSIS FOR SAFETY ASSESSMENT CALCULATION OF VVER UNIT MANEUVERING REGIMES EXPERIMENT

DOI: 10.55176/2414-1038-2021-1-55-65

Authors & Affiliations

Uvakin M.A., Nikolaev A.L., Makhin I.V., Sotskov E.V.
Experimental and Design Organization “GIDROPRESS”, Podolsk, Russia

Uvakin M.A. – Leading Design Engineer, Dr. Sci. (Phys.-Math.). *Contacts: 21, Ordzhonikidze st., Podolsk, Moscow region, Russia, 142103. Tel.: +7 (4967) 65-26-25; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Nikolaev A.L. – Design Engineer, category 3.
Makhin I.V. — Group Leader.
Sotskov E.V. – Head of Department.

Abstract

Maneuvering operation test is actual problem of VVER reactors exploitation. Such tests are classified as nuclear hazardous procedures which are accompanied by power variations, regulators actions and continuous space power field fluctuations. As a result a lot of possible initial reactor plant conditions are occurred. This fact should be taken into account during experiment safety assessment. Current work presents calculation analysis results for high powered VVER unit safety assessment which was covered daily maneuvering experiment. All calculations are implemented by KORSAR/GP programming code with 3D-neutrion kinetic model. Quantitative and qualitative criteria show the successful solving of following problems:
– Confirmation for normal operation limits adherence, especially for local power distribution parameters.
– Reactor plant safety assessment for RIA accidents.
Work contains analysis of developed method possibilities for VVER power unit calculation safety assessment during daily power maneuvering. Following criteria has been confirmed:
– All conservative approach principles completely comply which has composed usual VVER safety assessment method for 3D neutron kinetic model.
– All important features for reactor physics and dynamics during maneuvering have been taken into account.
Maneuvering regimes calculations practical and methodical experience will be applied for the same tasks of VVER safety assessment.

Keywords
calculation model, KORSAR/GP code, maneuvering regimes, reactivity accidents, safety assessment, dynamical initial condition

Article Text (PDF, in Russian)

References

UDC 621.039.56

Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2021, issue 1, 1:6