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Radiation Dose in a Reactor Service Area of the AP-1000 Based on the Fukushima Accident

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Radiation Dose in a Reactor Service Area of the AP-1000 Based on the Fukushima Accident Philippine Journal of Science 149 (3-a): 791-799, October 2020 ISSN 0031 - 7683 Date Received: 28 Jan 2020 Radiation Dose in a Reactor Service Area of the AP-1000 Based on the Fukushima Accident Rokhmadi1*, Ardani1§, Taswanda Taryo1, Muhammad Subekti1, Toshikazu Takeda2, and Arturo Failuga Salih3 1Center for Nuclear Reactor Technology and Safety – BATAN Kawasan PUSPIPTEK Gedung No. 80 Serpong Kota Tangerang Selatan 15310 Indonesia 2Nuclear Research Center, Fukui University, Fukui-ken, Japan 3Philippine Nuclear Research Institute, Department of Science and Technology Commonwealth Ave., Diliman, Quezon City, Philippines Cooling water as a radiation shield from a reactor core originates from the reactor core. In the case of an accident, when the cooling water level inside a pressure vessel decreases, the function of water as a radiation shield decreases as well. After the time passage of the reactor shutdown, the strength of gamma (γ) radiation source from the reactor core decreases. The combination of the decrease of the water that reduces the function of radiation shielding and the decrease of the source strength will affect the pattern of dose rate in the reactor service area (RSA) after an accident takes place. This paper discusses γ dose rate in an RSA of an advanced pressurized water reactor (PWR) (AP- 1000) nuclear power plant (NPP) based on the accident of Fukushima No. 1 reactor. The referred accident is the decrease in the level of cooling water until the it reached half of the height of the reactor core. The reactor core was not damaged since the γ source is still trapped in the matrix of the reactor core. The highest dose rate occurs when the water level decreases to the upper level of the reactor core. The dose rate above the pressure vessel at the RSA prior to the decrease of the water level was 0.7 rad/h, while the dose rate reached 740 rads/h when the water level reaches to the middle of the reactor core. Indeed, the dose rate at a point of 17.5 m horizontally from the center of the core tank was 0.057 rad/h. This condition requires highly selective control to enable entry to the area of the accident. Indeed, a large γ radiation rate due to a decline in the surface horizontal distance is around 6,404 times greater than those of cosmic and natural γ rays. Keywords: AP-1000 reactor, dose rate, Fukushima No-1 reactor, reactor service area, water cooling level decrease INTRODUCTION al. 2012). A nuclear accident that occurred in Fukushima No. 1 reactor becomes a basis to increase the efforts to Natural γ rays originate from cosmic radiation and from overcome the impact of the accident. This is due to the the earth itself and, according to the United Nations use of nuclear energy for the production of electricity, Scientific Committee on Atomic Radiation Securities, the which is one of the few options for future energy. While average dose rate is 89 nGy/h or 8.9 μrad/h (Hazrati et nuclear energy demand increases in the world (Krikorian *Corresponding Author: [email protected] and Evrensel 2017), fossil fuel supply is limited and has §Retired a serious impact to the environment (Purwadi 2010). To 791 Philippine Journal of Science Rokhmadi et al.: Radiation Dose in AP-1000 Reactor Service Area Vol. 149 No. 3-a, October 2020 construct a new NPP, nuclear safety aspects should be NPP’s RSA above the reactor pressure vessel (RPV). The AP- implemented and the impact of radiation from the plant 1000 is an NPP designed and sold by Toshiba-Westinghouse, to working areas, people operating the plant, and the and the AP-1000 is a PWR (a 1000-MWe PWR or PWR- environment should be determined. 1000) with the improvement of using passive nuclear safety. In addition, the fourth of the Chinese AP-1000 was launched Various studies have been conducted to examine the into operation in January 2019 (WNN 2019). Table 1 shows phenomena of accidents that occur, aimed at quantifying the main parameters of AP-1000. nuclear reactor safety against accidents to evaluate the effectiveness of reactor accident management actions. Main parameters of AP-1000 (Schulz 2008). According to the IAEA guidelines, planning for a reactor Table 1 accident management strategy requires input from the Parameter 2 SG/4 RCPs analysis of accident phenomena and analysis of their Net electric power, MWe 1,117 consequences (Udiyani et al. 2013). A nuclear accident Reactor power, MWt 3,400 at Fukushima No. 1 reactor decreased the water level in Hot leg temperature, °C 321 the reactor pressure vessel and, hence, this also implies a reduction of the radiation shield. The addition of the coolant Number of fuel assembly 157 in the primary cooling system of the reactor enhances the Type of fuel assembly 17 x 17 function of water as a radiation shield, especially for an Active fuel length, m 4.27 RSA, i.e. the area above the pressure vessel within the reactor Linear heat rating, kW/ft 5.71 containment. In addition, since the reactor automatically shut Control/gear rods 53/16 down due to the accident, there is no γ source formation from 3 the radiative-catch reaction and spontaneous fission reaction Vessel flow, m /h 68.1 in the reactor core. What remains is the decaying γ associated SG surface area (each), m2 11.1 with activation and fission products, and a higher level of Pressurizer volume, m3 59.5 actinides (Ardani 2007). SG – steam generator; RCPs – reactor cooling pumps The deteriorating aspect of the radiation shield function due to the decreasing water level and the strong decline The AP-1000 is a PWR-type reactor with two cooling in γ source activity inside the core is a significant reason loops to produce a net power output of 1,117 MWe. It is to determine the factor of radiation dose rate in the RSA an evolutionary improvement on the AP600 – essentially, a of an NPP. The Fukushima No. 1 nuclear reactor accident more powerful model with roughly the same footprint. The was categorized as a Level 7 disaster in the International design decreases the number of components – including Nuclear and Radiological Event Scale (Samet and Chanson pipes, wires, and valves. Because of its simplified design 2015). Although a Fukushima Daiichi NPP (Fukushima compared to a Westinghouse generation II PWR, the AP- No. 1) is a boiling water reactor (BWR), it is relevant 1000 has 50% fewer safety-related valves, 35% fewer to investigate a similar nuclear accident that may occur pumps, 80% less safety-related piping, 85% less control in PWR-1000 (a 1000-MWe PWR) or AP-1000 due to cable, and 45% less seismic building volume. In addition, similar general structure of the reactor. The chronology of probabilistic risk assessment was used in the design of the the Fukushima No. 1 reactor accident had been reported by plants and this enabled minimization of risks and calculation the NPP operator (Ardani 2007). The accident took place of the overall safety of the plant. From the safety calculation, since the occurrence of a power blackout of the reactor plant the AP-1000 has a maximum core damage frequency 5.09 brought about by an earthquake of 8.9 intensity (Richter × 10−7 per plant per yr. Power reactors principally remain scale). A 14-m-high tsunami generated by the earthquake to yield heat from radioactive decay products even after hit the plant with wave heights that temporarily inundated the main reaction is shut down; hence, it it is imperative to the station up to about 14 m above sea level, whereas the remove this heat to avoid a meltdown of the reactor core. In reactors were designed to withstand wave heights of 5.7 m. the AP-1000, Westinghouse's passive core cooling system As a result, the turbine building was flooded with salty sea uses a tank of water situated above the reactor. When the water, damaging the diesel-powered backup generator as passive cooling system is activated, the water flows by well as other emergency accessories of the reactors (Aliyu gravity to the top of the reactor where it evaporates to 2015). The cooling water level in the pressure vessel then remove heat. Although the reactor operators take no action, decreased to half of the height of the core. the system uses multiple explosively-operated and DC- As part of the lessons learned and review of nuclear operated valves, which must operate within the first 30 min. technology, particularly in radiation safety at the reactor, this The safety design is also intended to passively remove heat piece of accident information was applied to the AP-1000 for 72 h, after which its gravity drain water tank must be NPP (Schulz 2008) to predict the radiation dose rate in the topped up for as long as cooling is required. 792 Philippine Journal of Science Rokhmadi et al.: Radiation Dose in AP-1000 Reactor Service Area Vol. 149 No. 3-a, October 2020 a) PWR-1000 b) AP-1000 Figure 1. Safety systems of PWR 1000 and AP-1000 (Schulz 2008). It is noted that the structures of the building and pressure and photons that result directly from the fission process vessel, as well as the cooling water, of the PWR-1000 when the reactor is at power are referred to as prompt (AP-1000) reactor pressure vessel are very similar to neutrons and photons, decayed neutrons and photons that of the Fukushima No. 1 reactor, although the latter were also considered. is a BWR-type reactor.
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