Abstract

In Europe, the design extension conditions (DEC) were introduced after the Fukushima Dai-ichi accident as preferred method for giving due consideration to the complex sequences and severe accidents without including them in the design basis conditions. The objective of the study is to determine available elapsed time before core uncovery and needed DEC safety features for total loss of all feedwater (TLOFW) in a two-loop pressurized water reactor. RELAP5/MOD3.3 computer code has been used for calculations. The initiating event for TLOFW is multiple failures in which, in addition to the loss of main feedwater, the auxiliary feedwater is also lost. The scenarios without DEC safety features and the scenarios with DEC safety feature assumed have been simulated. The results showed that after TLOFW event initiation, it is very important to trip the reactor as soon as possible. In case of loss of offsite power, the reactor coolant pumps stop, and the reactor very quickly trips on low reactor coolant pump flow. When normal operation systems are assumed, the reactor trip occurs on low-low steam generator narrow level few tens of seconds after accident initiation, resulting in less time available before core uncovery occurence. The results for TLOFW scenarios with normal operation systems and DEC safety features assumed demonstrated that secondary side bleed and feed can prevent core uncovery in case when no operator actions are credited in the first 30 min of event. When primary side bleed and feed is used, less time is available for operator actions.

References

1.
Pierre Berbey
,
P.
,
1997
, “
The European Utility Requirement (EUR) Document in 1997, progress and perspectives
,”
Proceedings of the 5th International Conference on Nuclear Engineering
,
Nice, France
, May 26–30, Paper No. ICONE5-2446, p.
10
.
2.
WENRA RHWG
,
2007
, “
WENRA Reactor Safety Reference Levels
,” accessed July 13, 2023, p.
43
, https://www.wenra.eu/sites/default/files/publications/list_of_reference_levels_january_2007.pdf
3.
IAEA DS414
,
2011
, “
Safety of Nuclear Power Plants: Design Revision of IAEA Safety Standards Series No. NS-R-1, Draft Safety Requirements
,” Vienna, Austria, p.
67
.
4.
IAEA SSR-2/1
,
2012
, “
Safety of Nuclear Power Plants: Design, IAEA Safety Standards Series
,” Vienna, Austria, accessed July 13, 2023, p.
66
, https://www-pub.iaea.org/MTCD/Publications/PDF/Pub1534_web.pdf
5.
WENRA RHWG
,
2014
, “
WENRA Safety Reference Levels for Existing Reactors
,” accessed July 13, 2023, p.
52
, https://www.wenra.eu/sites/default/files/publications/wenra_safety_reference_level_for_existing_reactors_september_2014.pdf
6.
IAEA SSR-2/1 (Rev. 1),
2016
, “
Safety of Nuclear Power Plants: Design, IAEA Safety Standards Series
,” Vienna, Austria, accessed July 13, 2023, p.
71
, https://www-pub.iaea.org/MTCD/publications/PDF/Pub1715web-46541668.pdf
7.
WENRA RHWG
,
2021
, “
WENRA Safety Reference Levels for Existing Reactors 2020
,” accessed July 13, 2023, p.
58
, https://www.wenra.eu/sites/default/files/publications/wenra_safety_reference_level_for_existing_reactors_2020.pdf
8.
Prošek
,
A.
, and
Uršič
,
M.
,
2022
, “
Review of Design Extension Conditions Experiments and Analyses for Non-Degraded Core
,”
J. Energy
,
68
(
2–3
), pp.
112
125
.10.37798/2019682-3196
9.
Adams
,
J. P.
,
1981
, “
Quick-Look Report on Loft Nuclear Experiment L9-1/L3-3, Preliminary Data Analysis Report
,” Idaho Falls, Idaho, Report No. EGG-LOFT-5430 (NRC ADAMS Accession No. ML20008F788), p.
46
.
10.
Bang
,
Y. S.
,
Seul
,
K. W.
, and
Kim
,
H. J.
,
1994
, “
Assessment of RELAP5/MOD3 With the LOFT L9–1/L3–3 Experiment Simulating an Anticipated Transient With Multiple Failures, NUREG-Series Publications
,”
Publications Resulting From International Agreements NUREG/IA
,
Washington, DC
, Report No. NUREG/IA-0114, p.
116
.
11.
Prošek
,
A.
,
2018
, “
Simulation of L9-1/L3-3 Experiment With Multiple Failures on LOFT Facility
,” Proceedings of the 27th International Conference Nuclear Energy for New Europe (
NENE-2018
),
Portorož, Slovenia
, Sept. 10–13, Paper No. 316, p.
8
.https://arhiv.djs.si/proc/nene2018/htm/pdf/NENE2018_316.pdf
12.
Fell
,
J.
, and
Modro
,
S. M.
,
1990
, “
An Account of the OECD LOFT Project
,” U.S. Department of Energy Contract No. DE-AC07-76ID01570 for the OECD LOFT Project, Report No. OECD/LOFT-T-3908, p.
119
.
13.
Croxfod
,
M. G.
,
Harwood
,
C.
, and
Hall
,
P. C.
,
1992
, “
RELAP5/MOD2 Calculation of OECD LOFT Test LP-FW-01
,” NUREG-Series Publications, Publications Resulting from International Agreements NUREG/IA, Nuclear Regulatory Commission, Washington, DC, USA, Report No. NUREG-IA/0063, p.
52
.
14.
Choi
,
C.
,
Ha
,
K.-S.
, and
Kim
,
K. D.
,
2020
, “
Analyses of LOFT LP-FW-1 Using SPACE Code
,”
Ann. Nucl. Energy
,
135
, p.
107001
.10.1016/j.anucene.2019.107001
15.
Prošek
,
A.
,
2020
, “
RELAP5/MOD3.3 Simulation of LOFT LP-FW-1 Total Loss of Feedwater Test
,” Proceedings of the 29th International Conference Nuclear Energy for New Europe (
NENE-2020
),
Portorož, Slovenia
, Sept. 7–10, Paper No. 805, p.
8
.
16.
Clement
,
P.
,
Chataing
,
T.
, and
Deruaz
,
R.
,
1993
, “
PWR Accident Management Related Tests: Some Bethsy Results
,”
Proceedings of the 6th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURTEH-6)
,
Grenoble, France
, Oct. 5–8.
17.
Park
,
S. J.
,
Han
,
K. S.
,
Kim
,
C. W.
,
Choi
,
H. R.
, and
Kim
,
E. U.
,
2005
, “
Total Loss of Feedwater Analysis of Power Uprated Kori 3&4
,”
Transactions of the Korean Nuclear Society Autumn Meeting
,
Busan, Korea
, Oct. 27–28, p.
2
.
18.
París
,
C.
,
Queral
,
C.
,
Mula
,
J.
,
Gómez-Magán
,
J.
,
Sánchez-Perea
,
M.
,
Meléndez
,
E.
, and
Gil
,
J.
,
2019
, “
Quantitative risk reduction by Means of Recovery Strategies
,”
Reliab. Eng. Syst. Saf.
,
182
, pp.
13
32
.10.1016/j.ress.2018.09.024
19.
Hong
,
S. M.
,
Park
,
S. J.
,
Park
,
C. E.
,
Choi
,
J. H.
, and
Lee
,
G. C.
,
2016
, “
Analysis of Total Loss of Feedwater for APR1400 Using SPACE
,”
Transactions of the Korean Nuclear Society Autumn Meeting
,
Gyeongju, Korea
, Oct. 27–28, p.
3
.
20.
Kim
,
M. J.
,
Kim
,
M.
,
Lee
,
H.
, and
Choi
,
H.
,
2018
, “
Simulation Study of Total Loss of Feedwater in OPR1000 Using SPACE
,”
Transactions of the Korean Nuclear Society Spring Meeting
,
Jeju, Korea
, May 17–18, p.
3
.
21.
IAEA-TECDOC-1791
,
2016
, “
Considerations on the Application of the IAEA Safety Requirements for the Design of Nuclear Power Plants
,”
IAEA-TECDOC-1791, IAEA TECDOC Series
,
Vienna, Austria
, p.
88
.
22.
Prošek
,
A.
, and
Volkanovski
,
A.
,
2015
, “
RELAP5/MOD3.3 Analyses for Prevention Strategy of Extended Station Blackout
,”
ASME J. Nuc. Eng. Radiat. Sci.
,
1
(
4
), p.
10
.10.1115/1.4030834
23.
Prošek
,
A.
, and
Matkovič
,
M.
,
2018
, “
RELAP5/MOD3.3 Analysis of the Loss of External Power Event With Safety Injection Actuation
,”
Sci. Technol. Nucl. Install.
,
2018
, pp.
1
14
.10.1155/2018/6964946
24.
Parzer
,
I.
, and
Prošek
,
A.
,
2005
, “
Loss of Normal Feedwater Analysis for Krško Full Scope Simulator Validation
,”
Proceedings of the International Conference Nuclear Energy for New Europe 2005 (NENE-2005)
, Sept. 5–8,
Bled, Slovenia
, p.
9
, Paper No. 16.
25.
IAEA SSG-2 (Rev. 1)
,
2019
,
Deterministic Safety Analysis for Nuclear Power Plants, IAEA Safety Standards Series
(IAEA SSG-2 (Rev. 1)), International Atomic Energy Agency,
Vienna, Austria
, p.
118
.
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