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JAEA Reports

Evaluation on radioactive waste for the decommissioning of deuterium critical assembly(DCA)

Konno, Shotaro; Fukuda, Seiji; ; Hazama, Taira; ; Hashimoto, Makoto

JNC TN9410 2002-015, 59 Pages, 2002/10

JNC-TN9410-2002-015.pdf:2.3MB

Deuterium critical assembly (DCA) is a critical facility with 1 kW maximum thermal output reached its initial criticality in 1969. DCA operations were stopped on 26$$^{th}$$ September 2001, then it has been planed to submit a legal application for decommissioning of DCA to MEXT and to shift to decommissioning phase. In this work, we have evaluated the calculation value of neutron flux by comparison with an actual measurement in biological shield and the amount of contaminated radioactive materials etc. to make a document on estimation of the inventories and the wastes quantity etc. in the legal application. Results are as follows. (1)Fast, epithermal and thermal neutron flux calculated have exceeded the measurement data at almost all location. Therefore concentration of activated materials calculated by neutron flux calculation value is estimated higher than actual that. (2)The amount of radioactive materials that contaminated by nuclides other than tritium is estimated about 3.0$$times$$ 10$$^{7}$$Bq. The concentration of tritium-contaminated radioactive materials is estimated about 4.1$$times$$10$$^{1}$$Bq/g at the maximum in concrete, about 7.6 $$times$$ 10$$^{-2}$$Bq/g in the surface of aluminum plumbing. (3)Consequential waste quantity (solid waste) to radioactive waste generated in total process of dismantling is estimated about 30ton. As for Radioactive liquid waste quantity, moderator for specimen is estimated about 1.4m$$^{3}$$ , consequential liquid wastes is estimated about 300m$$^{3}$$. (4)The amount of Tritium generated in dismantling (radioactive gas waste) is estimated about 7.25$$times$$10$$^{8}$$Bq in dismantling of heavy water system facility, measurement control system facility and neutron reactor.

JAEA Reports

Discussion of dismantling system concept for liquid waste tanks in "Joyo" waste treatment facility

; Konno, Shotaro

JNC TN9410 2001-026, 106 Pages, 2002/01

JNC-TN9410-2001-026.pdf:4.53MB

Dismantling methods of contaminated liquid waste tanks have been developed for decommissioning of Joyo Waste Treatment Facility. In this report, we discussed a concept of dismantling system for the tanks using a water jet. Results are follows. (1)A water jet dismantling system is composed from dismantling work area, a water jet dismantling device, Waste tank moving device, Radioactive waste carrying device. (2)Evaporator room is appropriate for the dismantling work area. (3)A pressure intensifier with 400 MPa output pressure is choused for the dismantling device to decrease radioactive secondary wastes. (4)The waste tank moving device has a carrier used in a waste tank room and casters attached to the tanks when they are brought into the evaporator room to avoid cross contamination. (5)Radioactive waste carrying device is composed from a lifter, carrying containers, a green-house and a container-carrier. (6)2.5 tons of solid waste and 3.3 m$$^{3}$$ of liquid waste will be the secondary waste. (7)At points of developing working efficiency and decreasing the secondary waste, it is appropriate to break the tanks into large fragments and put them in 1 m$$^{3}$$ containers. (8)About 8 man*mSv is expected for whole dismantling works of the tanks. (9)Deliberate cutting of tanks will makes a filling ratio about 40%. (10)Introducing the water jet dismantling system, it is indispensable to decrease the secondary wastes including devices and introducing costs and to develop cost effectiveness much more.

JAEA Reports

Evaluation of activated inventories (II) in deuterium critical assembly (DCA)

; Konno, Shotaro; Tanimoto, Kenichi; Kondo, Hitoshi; Hazama, Taira;

JNC TN9410 2001-027, 136 Pages, 2001/12

JNC-TN9410-2001-027.pdf:6.9MB

Deuterium Critical Assembly (DCA) is a critical facility with 1 kW maximum themmal output used for development of an Advanced Thermal Reactor and a subcriticality measurement technique for criticality safety management of nuclear fuel facilities since its initial criticality in 1969. DCA operations were stopped on 26$$^{th}$$ September 2001, then it has been planed to submit a legal application for decommissioning of DCA and to shift to decommissioning phase. In this work, we have evaluated an amount of materials in all controlled areas, activated inventories and activated radioactive wastes to make a document on estimation of the inventories and the wastes et.al. in the legal application. Results are as follows. (1)Total amounts of materials in the controlled areas are 9,464 tons. An amount of concrete is 9,162 tons and greater than 97% of all materials in weight. (2)The radioactive inventories of metals et.al and a biological shield will be respectively l.39$$times$$ 10$$^{8}$$Bq and 4.90$$times$$10$$^{9}$$Bq in about 2008 when actual dismantling of components will be started. (3)We classified decommissioning materials according to clearance level that has been discussed to be legalized. An amount of low level radioactive wastes will be 36 tons. Amounts of clearanced or nonradioactive waste will be 9,428 ton and greater than 99% of all wastes in weight. 7,005 tons of concrete will be nonradioactive waste.

Oral presentation

Improvement of magnetic flux density measurement technique for irradiation damage evaluation

Konno, Shotaro; Takaya, Shigeru; Nagae, Yuji; Yamagata, Ichiro; Ogawa, Ryuichiro; Akasaka, Naoaki; Nishinoiri, Kenji

no journal, , 

We are developing a method for evaluation of irradiation damage on structural materials in nuclear plants by using change in magnetic flux density due to irradiation damage. In this study, the magnetic flux density measurement technique has been improved by introducing a new magnetizer which enables local magnetizing by contacting the sample surface, and the calibration method of the flux gate sensor for the magnetic flux density. We can magnetize samples, especially ferromagnetic samples, more precisely compared to the existing method. Furthermore, the new method can remove many limitations for the application to real plants.

Oral presentation

Improvement of magnetic flux density measurement technique for irradiation damage evaluation

Konno, Shotaro; Takaya, Shigeru; Nagae, Yuji; Yamagata, Ichiro; Ogawa, Ryuichiro; Akasaka, Naoaki; Nishinoiri, Kenji

no journal, , 

We are developing a method for evaluation of irradiation damage of structural materials in nuclear plants by using change in magnetic flux density due to irradiation damage. In this study, the magnetic flux density measurement technique has been improved by introducing a new magnetizer which enables local magnetizing by contacting the sample surface. We can magnetize samples, especially ferromagnetic samples, more precisely compared to the existing method. Furthermore, the new method provided the path for the application to real plants.

Oral presentation

Evaluation of neutron irradiation damage based on magnetic properties

Takaya, Shigeru; Yamagata, Ichiro; Konno, Shotaro; Ichikawa, Shoichi; Ogawa, Ryuichiro; Nagae, Yuji

no journal, , 

We measured the magnetic flux densities and the magnetization curves on neutron irradiated fast reactor grade type 316 stainless steels by a flux gate sensor and a newly developed vibrating sample magnetometer, respectively. As the result, it was revealed that there is a good relationship between magnetic property and dose, one of representative irradiation damage parameters. This result shows the possibility of nondestructive evaluation of neutron irradiation damage based on magnetic properties.

Oral presentation

Magnetic property variation of the austenitic stainless steels irradiated in JOYO

Hayashi, Takehiro; Takaya, Shigeru; Nagae, Yuji; Konno, Shotaro; Yamagata, Ichiro

no journal, , 

Structural materials in nuclear plants are affected to aging degradation and irradiation damage. Nondestructive measurement of materials damage is a preferred method for the diagnosis of nuclear plants. The previous studies are focused on magnetic property, which is able to measure by nondestructive and sensitive for microstructure and variation of local chemical compositions. However, whole sample is needed to magnetize by large magnets in the previous method, and the sample is easily influenced by magnetic flux at the edge of sample. This issue makes magnetic method difficult to apply to nuclear plants. The pointing magnetization technique was developed for a local magnetization of samples with a small magnet. It is the first time to apply this method on austenitic stainless steels for fast reactor structural material. The measurement results show that austenitic steels have increased magnetic flux density as dose increases. And magnetic flux density is dependent on irradiation temperature. These results indicate pointing magnetize technique suggested the possibility of the irradiation damage evaluation of austenitic stainless steel.

Oral presentation

Nondestructive evaluation of neutron irradiation damage on austenitic stainless steels by measurement of magnetic flux density

Takaya, Shigeru; Nagae, Yuji; Aoto, Kazumi; Yamagata, Ichiro; Ichikawa, Shoichi; Konno, Shotaro; Ogawa, Ryuichiro; Wakai, Eiichi

no journal, , 

Magnetic flux densities for neutron irradiated specimens of austenitic stainless steels were measured by using a flux gate (FG) sensor to investigate the nondestructive evaluation method of irradiation damage parameters, dose and He content. The range of dose, He content and irradiation temperature of the neutron irradiated samples studied in this paper were 0.01-30 displacement per atom (dpa), 1.0-17 appm and 470-560 $$^{circ}$$C, respectively. Magnetic flux density increased with dose although there may be a threshold dose for magnetic property to change between 2 and 5 dpa for 316FR. This result shows the possibility of nondestructive evaluation of dose by measuring magnetic flux density by an FG sensor. On the other hand, magnetic flux density did not depend on He content.

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