THE PROBLEM
Probably you fully trust in the safety of your nuclear plants… as the TEPCO managers did before 2011 .
Fukushima taught us that there are some situations not properly evaluated yet or even poorly solved.
I have to forewarn you about a risky event awaiting to complicate an -always undesirable- nuclear accident.
This event is already know as the tsunamis, but it is still not properly solved. This is the undesired Nitrogen Injection to the core from the safety accumulators.
This event can hapen during the worst accident than a nuclear plant could to face: The Extended Loss of Ac Power (ELAP) or also known as Station BlackOut (SBO).

WE HAVEN’T DISCOVERED THE NITROGEN PROBLEM!!
We’re just a company GIVING A GOOD SOLUTION!
There are a lot of scientific papers talking about the harmful effects of the uncondensable gases inside the Reactor Cooling System. Here are some interesting links:
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NEW 2025: G.Verdú et al, 2025. Analysis of nitrogen intrusion from ECCS accumulators in SBLOCA scenarios at LSTF test facility. Progress in Nuclear Energy 189 (2025) 105954 URL https://www.sciencedirect.com/science/article/pii/S014919702500352X
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NEW 2025: Vesa Riikonen, Virpi Kouhia et al, 2025. Experimental studies on nitrogen’s effect on reactor core cooling during a hot leg SBLOCA in a scaled EPR model. Nuclear Engineering and Design 434 (2025) 113916 URL https://www.sciencedirect.com/science/article/pii/S0029549325000937
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US-NRC, 2008. NRC Generic Letter 2008-01: Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. URL https://adamswebsearch2.nrc.gov/webSearch2/main.jsp?AccessionNumber=ML072910759
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MARTIN STEINBRUECK, FABIO OLIVEIRA DA SILVA, MIRCO GROSSE, Oxidation of Zircaloy-4 in steam –nitrogen mixtures at 600-1200ºC, Journal of Nuclear Materials 490 226-237 (2017). https://www.scinapse.io/papers/1944675303
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MARINA LASSERRE, VERONIQUE PERES, JEAN-PAUL MARDON, Modelling of Zircaloy-4 accelerated degradation kinetics in nitrogen-oxygen mixtures at 850 °C, Jul 1, 2015 Journal of Nuclear Materials.https://www.scinapse.io/papers/2087758060
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MARTIN STEINBRÜCK, ALEXEI MIASSOEDOV, GERHARD SCHANZ, LEO SEPOLD,ULRIKE STEGMAIER, JURI STUCKERT, Experiments on air ingress during severe accident, 13th International Conference on Nuclear Engineering Beijing, China, May, 2005. URL: http://citeseerx.ist.psu.edu/viewdoc/download?doi=10.1.1.707.3229&rep=rep1&type=pdf
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Gases on Circulation of Primary Coolant in Nuclear Power Plants in Abnormal Situations (Thesis for the degree of Doctor of Science (Technology), Lappeenranta University of Technology (Finland), (2003). URL: https://lutpub.lut.fi/handle/10024/31154
CHRISTINE SARRETTE, Effect of Noncondensable -
RIIKONEN, VESA, KOUHIA, VIRPI, KAUPPINEN, OTSO-PEKKA, SJÖVALL, HEIKKI, HYVÄRINEN, JUHANI, System code analysis of accumulator nitrogen discharge during LOCA experiment at PWR PACTEL test facility. Nuclear Engineering and Design, November 2019. https://www.researchgate.net/publication/336961146_System_code_analysis_of_accumulator_nitrogen_discharge_during_LOCA_experiment_at_PWR_PACTEL_test_facility
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MITSUHIRO SUZUKI, TAKESHI TAKEDA, HIDEAKI ASAKA, AND HIDEO NAKAMURA, Experimental study on secondary depressurization action for PWR vessel bottom small break loca with HPI failure and gas inflow (ROSA-V/LSTF test SB-PV-03): URL:https://inis.iaea.org/collection/NCLCollectionStore/_Public/37/009/37009892.pdf?r=1&r=1
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B.NOEL R.DERUAZ, Reflux condenser mode with non-condensible gas: assessment of Cathare against Bethsy test 7.2C, Nuclear Engineering and Design Volume 149, URL:https://www.sciencedirect.com/science/article/abs/pii/002954939490295X
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PAVEL KRAL, JUHANI HYVARINEN, ANDREJ PROSEK, ATTILA GUBA, Sources and Effects of Non-Condensable Gases in Reactor Coolant System of LWR, NURETH-16, Chicago, 2015, URL: https://www.researchgate.net/publication/281492581_SOURCES_AND_EFFECT_OF_NON-CONDENSABLE_GASES_IN_REACTOR_COOLANT_SYSTEM_OF_LWR
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RIIKONEN, VESA, KOUHIA, VIRPI, KAUPPINEN, OTSO-PEKKA, SJÖVALL, HEIKKI, HYVÄRINEN, JUHANI, Experimental observation of adverse and beneficial effects of nitrogen on reactor core cooling. Nuclear Engineering and Design June, 2018, URL:https://www.researchgate.net/publication/325502268_Experimental_observation_of_adverse_and_beneficial_effects_of_nitrogen_on_reactor_core_cooling
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LI YUQUAN, HAO BOTAO, ZHONG JIA, AND WANG NAN, Comparative Experiments to Assess the Effects of Accumulator Nitrogen Injection on Passive Core Cooling During Small Break LOCA, Nuclear Engineering and Technology 49 54-70 (2017). URL:https://www.sciencedirect.com/science/article/pii/S1738573316301012
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VARIOUS AUTHORS, Various incidents in the US plants related with nitrogen. IN-97-40, IN-89-67, ML031050497, ML031060539, ML031180745, ML090980303.
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TAKESHI TAKEDA, AKIRA OHNUKI, DAISUKE KANAMORI, AND IWAO OHTSU, ROSA/LSTF Tests and RELAP5 Posttest Analyses for PWR Safety System Using SG’s Secondary – Side Depressurization against Effects of Release of Nitrogen Gas Dissolved in Accumulator Water, Science and Technology of Nuclear Installations Volume 2016, Article ID 7481793.URL:https://www.researchgate.net/publication/303830803_ROSALSTF_Tests_and_RELAP5_Posttest_Analyses_for_PWR_Safety_System_Using_Steam_Generator_Secondary-Side_Depressurization_against_Effects_of_Release_of_Nitrogen_Gas_Dissolved_in_Accumulator_Water
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NRC Information Notice No. 89-67: Loss of Residual Heat Removal Caused by Accumulator Nitrogen Injection, URL: https://www.nrc.gov/reading-rm/doc-collections/gen-comm/info-notices/1989/in89067.html
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RIHAN, M. TEAMAH, M. SOROUR, S. SOLIMAN, Codensation during nuclear reactor LOCA. 6th Conference on Nuclear and Particle Physics Nov. 2007 Luxor, Egypt URL:https://inis.iaea.org/search/search.aspx?orig_q=RN:40081094
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ROMAN MUKIN, IVOR CLIFFORD, OMAR ZERKAK, HAKIM FERROUKHI Modeling and analysis of selected organization for economic cooperation and development PKL-3 station blackout experiment using TRACE. Nuclear Engineering and Technology 50 (2018) URL:https://www.sciencedirect.com/science/article/pii/S1738573317305727
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VARIOUS AUTHORS, WCAP-17601-P Rev.1, Reactor Coolant System Response to the Extended Loss of AC Power Event for Westinghouse, Combustion Engineering and Babcock & Wilcox NSSS Designs, Westinghouse Proprietary Class 2, (2013).
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VARIOUS AUTHORS, FSG-10 Rev.1, Passive RCS injection isolation. Background information for Westinghouse Owners Group Emergency Response Guidelines, PWROG Proprietary Class 2, (2014).
THE ELAP (or SBO) ACCIDENT
A risky accident in a Nuclear Reactor is the Extended Loss of AC Power accident (ELAP). This accident is also known as Station Black-Out (SBO). At this accident, the control of ALL the equipment in the plant is completely lost for a long time. This happened at Fukushima with their catastrophic consequences.
But this accident has a worse side; it directly leads to another serious accident: The Loss of Coolant Accident (LOCA).
After a few minutes, the high temperature reached will degrade the Reactor Coolant Pump seals. Then, it will begin a moderate -but continuous- loss of coolant across these damaged seals. This leak will be PERMANENT during all the time. But not just during the accident event… also during the whole recovery time. Only when operators can access again to the containment building, this leak can be fixed… ant this can take years!
The safety accumulators inject soon their borated water, recovering during some time the leaked coolant… This is good while there is water inside the accumulators.
But sooner or later, the water runs out. Now the pressurized nitrogen which has driven the water injection, begins entering into the cooling system. This Nitrogen injection will complicate the accident recovery disturbing the cooling systems.
This is a bad situation, because this nitrogen in the cooling circuit will produce further problems such as disturbing the Natural Cooling, increasing the pressure, and greatly increasing the chances of core melting.
Once this nitrogen reaches the pipes, it will remain inside during the rest of the accident, disturbing all the cooling efforts even during the long recovery time.
It’s a similar situation when an air bubble gets into a vein. It will disturb the normal blood circulation. If the bubble is big enough, it can permanently stop the blood flow. It’s the embolism that can lead to the death.
It’s easy to understand that avoiding this undesired nitrogen injection is a very important task to recover the reactor’s safety.
WHY NITROGEN IS A DANGEROUS THREAT?
-Having nitrogen in the system cooling pipes is a very dangerous situation, as it can greatly difficult the core cooling.
- It can permanently stop the “natural circulation” flow. This is the main way to cool the core in these circumstances. Natural circulation is a physical process that produces a constant flow from the core to the heat exchangers without the need for pumps. It’s a passive way to extract the core heat.
- It also can make difficult another cooling mode named “reflux cooling”. Nitrogen will diminish the steam condensation in the Steam Generator tubes, increasing the temperature in the core.
- It will increase (and maintain) the pressure in the system. This gas will be heated by the steam from the core. This will increase the pressure in the system increasing the leak and avoiding that the low-pressure safety pumps (LPSI) can recover the core level.
- It will accelerate the fuel degradation. If the core temperature rises enough, the nitrogen presence will accelerate the fuel cladding oxidation, diminishing the time available to avoid the core damage.
- It can disturb the recovering pumps. Sooner or later the power will be restored again. But with the nitrogen inside, it can reach the cooling pumps and cause them to become air bound with little or no flow, rendering the pump inoperable. Air binding can affect more than one pump when pumps share common discharge or suction headers or when the gas accumulation process affects more than one train. This situation will greatly increase its risk significance.
- Gas accumulation can result in water hammer or pressure transients, particularly in pump discharge piping following a pump start, which can cause piping and component damage or failure.
IT’S LIKELY TO SUFFER THIS PROBLEM?
Unfortunately, this situation has a high probability of happening.
Why can I say that?
- Because this nitrogen is already inside the system, and there is a big quantity of it stored in the accumulators.
- It has an open and direct path to the core.
- Nitrogen is constantly trying to get into the pipes. It just needs a moment of low pressure in the system…
- And this pressure always tends to go to the atmospheric pressure. As the leaks are permanent, sooner or later the system will become atmospheric.
- The isolation valve which can close the path to the core, is maintained de-energized and locked in the open position, so it has to be energized, unlocked, and closed.
- But this valve is a big valve (12”) with a big seal, and it is not designed to manage gas… so it will leak this nitrogen to the core.
So it’s a matter of time that nitrogen gets into the pipes. Do you agree with me?
HOW BIG IS THE PROBLEM?
Then, it’s easy to understand that the nitrogen injection is a dangerous complication, but… How much?
We can do some simple calculations:
Each accumulator has around 14 m3 of nitrogen (@ 45 Bar @ 35ºC). This means around 640 kilograms. This nitrogen obviously follows the ideal gases laws (P * V = n * R * T), and during the accident its temperature T will rise in the system, and at the same time, the leaks will make the pressure P falling continuously.
This means that this nitrogen will expand a lot. From the initial volume of 14 m3, It can reach until 585 m3 (@ 1 Bar @ 35ºC).
On the other side, the total volume of the RCS is around 340 m3 at 4 loop plants. At 3 loop plants or 2 loop plants, it is even smaller.
This means that just one accumulator has enough nitrogen to fill the whole RCS volume. But this can be worse, because there is one accumulator in each loop.
Then, the problem can be THREE OR FOUR TIMES BIGGER!!!. Nitrogen can easily fill the entire RCS volume displacing the water. There is too much nitrogen inside the accumulators!!
And all this nitrogen has a DIRECT PATH to the core! It will constantly disturb the core cooling from its inside.