Analysis of Computer Modelling Results on Fuel Rods Strength and Condition at Reduced or Absent Cooling Caused by Accident

2021;
: pp. 7 – 16
https://doi.org/10.23939/jeecs2021.01.007
Received: January 05, 2021
Revised: February 17, 2021
Accepted: February 23, 2021

S. Lys. Analysis of computer modelling results on fuel rods strength and condition at reduced or absent cooling caused by accident. Energy Engineering and Control Systems, 2021, Vol. 7, No. 1, pp. 7 – 16. https://doi.org/10.23939/jeecs2021.01.007

Authors:
1
Lviv Polytechnic National University

The paper describes the phenomenology of fuel rod behaviour in severe accident. As an example, an experiment is described resulting in severe damage of 19 fuel rod assembly of VVER type; it was carried out in the CORA facility in 1993 (Research Centre, Karlsruhe, Germany). Testing conditions and results of post-test investigations of fuel assembly are given. The fuel rod code RAPTA-SFD is briefly dealt with; the code was a participant in the International Standard Problem ISP-36. The basic results are presented acquired by computer modelling CORA-W2 experiment using RAPTA-SFD code. Among the presented experimentally acquired and calculated results, the scope of the data on stainless steel component behaviour is substantial. The tested CORA-W2 fuel assembly contained a significant quantity of steel components, viz., spacer grids, a guide thimble, and a cladding of an absorber element. It is to be borne in mind that the spacer grids and a guide thimble of the updated and upgraded fuel assembly of VVER-1000 are fabricated from Zr-alloy, hence, the relative quantitative characteristics of chemical interactions between materials and stainless steel (Cr-Ni alloy) will be much lower for the up-to-date upgraded fuel assembly under identical conditions.

  1. Nuclear safety rules for nuclear power plants. PBYA RU AS-89. PNAE G-1-024-90. (in Russian)
  2. General provisions for ensuring the safety of nuclear power plants OPB-88/97. NP-001-97 (PNAE G-01-011-97). Approved by the Resolution of the Gosatomnadzor of Russia N9 of 11/14/97. (in Russian)
  3. Firnhaber M., Trambauer K., Hagen S., Hofmann P., Yegorova L. Specification of the International Standard Problem ISP36: CORA-W2 Experiment on Severe Fuel Damage. February 1994.
  4. International  Standard  Problem  ISP-36:  CORA-W2  Experiment  on  Severe  Fuel  Damage  for  a  Russian  Type  PWR.  Comparison  Report. OCDE/GD(96)19, GRS-120, FZKA 5711.
  5. NPP “KUDANKULAM” Unit 1,2. Topical report «Results of computer modelling fuel rods  strength and condition in accidents attended with deteriorated cooling or loss of coolant (postulation cladding temperature rise up to melting point)» SE VNIINM, 2001.
  6. Bibilashvily Yu.K., Sokolov N.B., Salatov A.V., Andreyeva-Andrievskaya L.N., Nechaeva O.A., Vlasov F.Yu. Features of RAPTA-SFD code modelling of chemical interactions of basic materials of the VVER active zone in accident conditions with severe fuel damage. Proceedings of IAEA Technical Committee on Behaviour of LWR Core  Materials under Accident Conditions, held in Dimitrovgrad, Russia, on 9-13 October  1995.  IAEA-TECDOC-921, Vienna, 1996,  pp. 243-252.
  7. Hofmann P., Uetsuka H., Wilhelm A.N., Garcia E.A. Dissolution of solid UO2 by molten zircaloy  and  its  modelling.  In: Severe Accidents in Nuclear Power Plants, Proceedings of a Symposium,  Sorrento,  21-25 March 1988,  Jointly organized by IAEA and NEA (OECD), IAEA-SM-296/1, pp. 3-17.
  8. Goryachev A., Shtuckert Yu., Zwir E., Stupina L. Post-test investigation result on the VVER-1000 fuel tested under severe accident conditions. Proceedings of IAEA Technical Committee on Behaviour of LWR Core Materials under Accident Conditions, held in Dimitrovgrad, Russia, on 9-13 October  1995.  IAEA-TECDOC-921, Vienna, 1996,  pp. 187-202.