Vol. 3 No 3 was published on September 23, 2019. | Clarivate Analytics | Control Committee in Education and Science of the Republic of Kazakhstan |


Safety analysis for the WWR-K research reactor converted to LEU fuel
 

Number 3_Vol.3

AUTHORS: S.N. Koltochnik, A.A. Shaimerdenov

DOI: 10.29317/ejpfm.2019030302

PAGES: 204 - 218

DATE: 2019-09-23


ABSTRACT

Recently in the WWR-K water-water research reactor the former HEU fuel, enriched to 36% in Uranium-235, was changed to LEU one, enriched to 19.7%, with substantial change of the core configuration. In view of reactor conversion, a new Safety Analysis Report (SAR) was developed for the WWR-K reactor. Substantiation of reactor safe operation under both normal operation and emergency conditions was done under thermal-hydraulic approach. In the analysis developed prior to physical start up it was assumed that a main circulation pump (MCP) provides the coolant flow rate in the core equal to 350 m3 /h (a certified value for the pump CB-321). However, in course of the reactor physical start up it was found that it is only 250 m3 /h. The reason was a decision of the reactor staff to reduce the primary pump power consumption, prolonging its life time.Therefor the thermal hydraulic analysis was revised, and the SAR was renewed. Safety analysis implies also consideration of some potential initiating events capable to develop into an accident. So, several typical initiating events are subject to thermal-hydraulic analysis to
substantiate observance of nuclear and radiation safety in emergency situations. It is shown that, owing to proper operation of safety systems, the initiating events under consideration don’t result into accidents, if two primary pumps provide not more than 585 m3 /h.
 


KEYWORDS

research reactor, LEU fuel, safety analysis report, thermal-hydraulic analysis, fuel assembly, ONBR, coolant flow rate, steady states, transients.
 


CITED REFERENCES

[1] S.N. Koltochnik et al., Preprint of Institute of Nuclear Physics (Almaty, Kazakhstan) (2016) Preprint 43, 58 p. (in Russian)
[2] S. Koltochnik, A. Shaimerdenov, Proceeding of the RERTR-2015International Meeting, Seoul (2015) 26.
[3] J.F. Briesmeistere, A General Monte Carlo N-Particle Transport Code. Los Alamos National Laboratory (2008) LA-UR-03-1987.
[4] P. Arne et al., User’s Guide to the PLTEMP/ANL V4.2Code. Argonne National Laboratory (2011).
[5] A.P. Olson et al., User’s Guide to PARET/ANL Version 7.5 r82160803. Nuclear Engineering Division, Argonne National Laboratory (2016).
[6] S. Koltochnik et al., Proceedings of the RERTR-2005 Meeting, Boston (2005) 117.
[7] S. Koltochnik et al., Proceedings of the RERTR-2006 Meeting, Cape Town (2006) 13.
[8] F.M. Arinkin et al., Proceedings of the International Conference RERTR-2010 Lisbon (2010) 120.
[9] A. Shaimerdenov et al., NNC RK Bulletin 4 (2010) 59. (in Russian)
[10] A.O. Bejsebaev et al, Mir nauchnyh issledovanij 8-9(50-51) (2011) 32. (in Russian)
[11] F. Arinkin et al., Proceedings of the RERTR-2012, Warsaw (2012) 54.
[12] F. Arinkin et al., Izvestija Tomskogo politehnicheskogo universiteta. Serija: Tehnika i tehnologii v jenergetike (2014) 325(4) 6. (in Russian)
[13] N.A. Hanan, P.L. Garner, Neutronic, Technical Report ANL/RTR/TM-15/7, US Argonne National Laboratory (2015) DOI:10.2172/1214274.
[14] A.A. Shajmerdenov et al., Al’ternativnaja jenergetika i jekologija 10-12 (258-260) (2018) 23. (in Russian)


Download file Open file