Available online at www.sciencedirect.com Physics Procedia 43 (2013 ) 307 313 The 7 th International Topical Meeting on Neutron Radiography Design of the testing set-up for a nuclear fuel rod by neutron radiography at CARR Guohai Wei, Songbai Han *, Hongli Wang, Lijie Hao, Meimei Wu, Linfeng He, Yu Wang, Yuntao Liu, Kai Sun, Dongfeng Chen China Institute of Atomic Energy, P.O.Box 275(30), Beijing, 102413, China Abstract In this paper, an experimental set-up dedicated to non-destructively test a 15cm-long Pressurized Water Reactor (PWR) nuclear fuel rod by neutron radiography (NR) is described. It consists of three parts: transport container, imaging block and steel support. The design of the transport container was optimized with Monte-Carlo Simulation by the MCNP code. The material for the shell of the transport container was chosen to be lead with the thickness of 13cm. Also, the mechanical devices were designed to control fuel rod movement inside the container. The imaging block was designed as the exposure platform, with three openings for the neutron beam, neutron converter foil, and specimen. Development and application of this experimental set-up will help gain much experience for investigating the actual irradiated fuel rod by neutron radiography at CARR in the future. 2013 The Authors. 2013 The Published Authors. by Elsevier Published B.V. Open by access Elsevier under CC Ltd. BY-NC-ND license. Selection and/or Selection peer-review and/or under peer-review responsibilty under of ITMNR-7 responsibility of ITMNR-7 Keywords: neutron radiography, non-destructive testing, Pressurized Water Reactor (PWR), nuclear fuel rod, CARR 1. Introduction Neutron radiography (NR) is a Non-Destructive Testing (NDT) technique, considered to be complementary to X-ray and gamma radiography, which is an essential tool for defect determination and analysis of irradiated fuel rods from nuclear reactors [1-3]. Compared with X-rays, the ability of the neutron to penetrate uranium is considerably higher, so the inner structures of the fuel rod can be inspected. Furthermore, the probability of a neutron interaction with hydrogen is very high, whilst that of X-rays can be neglected. Neutron radiography can be used for studying the phenomenon of hydrogen ingress, which is one important mechanism for cladding embrittlement, investigating the absolute * Corresponding author. E-mail address: hansb@ciae.ac.cn. 1875-3892 2013 The Authors. Published by Elsevier B.V. Open access under CC BY-NC-ND license. Selection and/or peer-review under responsibilty of ITMNR-7 doi:10.1016/j.phpro.2013.03.036
308 Guohai Wei et al. / Physics Procedia 43 ( 2013 ) 307 313 hydrogen content and its distribution [2, 4]. Neutron radiography has been used as an NDT technique since the 1950s [5]. Since the early 1970s, neutron radiography has been routinely used for the quality control for nuclear fuels [6]. Located at the Idaho National Laboratory (INL), a 250 kw Training Research Isotope General Atomics (TRIGA) reactor built in the Hot Fuel Examination Facility (HFEF) was used to examine the internal features of fuel rods neutron radiography [7]. The Japanese and Spanish nuclear industries conducted joint experimental programmes in the early 1990s to study high burnup samples, including inspecting pellet structures by NR [8]. A special set-up named NEURAP (NEUtron Radiography of Activated Probes) was used for both transportation and investigation of actual fuel at the NR facility of PSI (Paul Scherrer Institute) located at the Swiss spallation neutron source SINQ [1]. 2. The set-up at CARR s neutron radiography facility A new research reactor called China Advanced Research Reactor (CARR) has been constructed in the China Institute of Atomic Energy (CIAE) in China. CARR is a beam type of research reactor with a power of 60 MW [9]. A thermal neutron radiography facility based on CARR has been designed (Fig. 1). Thermal neutrons from the reactor was designed to be collimated by a divergent collimator with a length/inner diameter (L/D) ratio of 300-1200, and the max neutron flux at the sample position was calculated to be about 1 10 9 n/cm 2 s. Fig.1. Design of the thermal neutron radiography facility at CARR The indirect neutron radiography method has been applied to investigate irradiated fuel samples because of the strong radiation dose rate [1-3]. In order to study this method, a special set-up for testing a 15cm-long actual irradiated PWR nuclear fuel rod has been designed and fabricated at CARR. This consists of a transport container, an imaging block and a steel support (Fig. 2). A 15cm-long dummy fuel rod used as the specimen instead of the actual one has been fabricated, the cladding is made of aluminum with the outer diameter of 1cm and thickness of 0.5mm, and several 1cm-long pins made of lead are filled in.
Guohai Wei et al. / Physics Procedia 43 ( 2013 ) 307 313 309 Fig.2. Diagrammatic sketch of the set-up for inspection of a nuclear fuel rod 3. Design of the transport container The main functions of the transport container are shielding the specimen s radiation during the transportation and experiment and controlling its movements. There are two major requirements for the transport container; one is that the shielding must be sufficient to minimize the radiation level at the surface of the container due to the radio-active fuel rod whilst the other is that movements of the fuel rod must be controlled by automatic mechanical devices during testing. 3.1. Shielding design by MCNP Code In order to avoid exposure of the operating personnel to radiation from the irradiated fuel, a shielding simulation of the transport container was performed using the MCNP4C code, which is a general purpose Monte Carlo code for calculating the time dependent multi-group energy transport equation for neutrons, photons and electrons in three dimensional geometries [10]. For the simulation, the model included a shell as the shielding layer and a fuel rod located in the center of the model as the radiation source (Fig. 3). The radiation data of a typical actual irradiated PWR fuel rod (burnup 33GWd/tU, U-235 enrichment 3.5%, cooled for 1 year, chosen a 15cm-long section) was used as the data of the radiation source instead of the dummy fuel rod [11]. Less than 3 Sv/h of the dose equivalent rate at 5cm from the outer face of the shell was chosen as the safety standard. The material and thickness of the shell were altered to get a series of simulation results. From the simulation results (Fig. 4), the material of the transport container shell was selected to be lead with a thickness of 13 cm. Fig.3. MCNP model of the transport container
310 Guohai Wei et al. / Physics Procedia 43 ( 2013 ) 307 313 Fig.4. Simulation results of the transport container. Four kinds of materials (Fe, Lead, W and U-238) and a series of thicknesses of the shell were simulated 3.2. Design of mechanical devices In order to control the fuel rod s movement and fix its position, a mechanical grip was designed to fix and release the fuel rod by two 1/4-circle claws, as shown in Fig. 5. Clamping/releasing of the claws is controlled by the driving bar and the movement of the grip was controlled by the screw bar, as shown in Fig. 6. With the grip, the transport container can control the fuel rod s movement over 45cm along the vertical direction with 1mm accuracy. Fig.5. Construction of the mechanical grip Fig.6. Design of the transport container The transport container was chosen to be a cylinder shell with the outer diameter of 53cm and the total height of 120cm, the inner space is empty for the mechanical devices with the inner diameter of 25cm and the height of 60cm. The outer layer of the shell is made of stainless steel, and 13cm-thick lead was filled
Guohai Wei et al. / Physics Procedia 43 ( 2013 ) 307 313 311 in. A circular hole with the diameter of 3cm at the bottom was designed as the path to guarantee the fuel rod moving out/into the neutron beam by the grip. A sliding shielding section at the bottom was designed to open/close the hole, which was designed as a concavo-convex shape to avoid radiation leakage. 4. Design of the imaging block The indirect neutron radiography investigation must be performed in two independent steps. First, the neutron beam is lead onto the fuel rod and the converter foil behind. After the exposure the converter foil will be placed directly on a radiation sensitive detector (X-ray film or imaging plate) by mechanical devices to obtain the neutron radiography image of the fuel rod [2]. The imaging block, as shown in Fig. 7, is the exposure platform for the first step of indirect neutron radiography, and the transport container is docked on top of it. It was designed as a cube with the size of 90cm in all directions, with three entrances on it [1]. The horizontal entrance for the neutron beam faces the direction of the neutron beam coming from the thermal neutron radiography facility. The height of this entrance was designed as 11cm, for the height of the neutron beam is 11cm (design figure). The width is 3cm to match the diameter of the fuel rod (1cm), and its depth is 60cm. The vertical entrance was designed as a cylinder hole with the diameter of 3cm to receive the fuel rod. Because the height of the neutron beam is 11cm whilst the length of the fuel rod is 15cm, it is necessary to carry out two shots to complete the inspection of the whole fuel rod by changing its position. The converter foil made of 0.1mm-thick indium supported by 1mm-thick aluminum (99.5% purity) plate has been fabricated [3]. The height of the converter foil is 11cm and the width is 10cm. The entrance for the converter foil is vertical to the neutron beam entrance and just behind the entrance of the fuel rod with the distance of 0.5mm. The height of the entrance is 11cm, the width is 0.7cm, and the depth is 60cm. A track has been mounted at the bottom of the entrance so as to support and move the converter foil automatically by the remote control system. The imaging block s shell was made by 2cm-thick stainless steel, and it was filled with heavy concrete (the density is 4.6 g/cm 3 ), after the three designed entrances had been amounted and fixed. In order to constrain the area of the neutron beam and absorb unwanted neutrons, an 8cm-thick boron-polythene plate was embedded into the front side (face to the neutron beam) with the area of 20cm by 20cm. Fig.7. Construction of the imaging block
312 Guohai Wei et al. / Physics Procedia 43 ( 2013 ) 307 313 Fig.8. Section view of the imaging block Fig.9. The fabricated set-up Finally, a steel platform on the ground was designed for supporting the transport container and the imaging block. 5. Conclusion At the time of submitting this paper, the construction of the set-up (Fig. 9) had been completed and alignment adjustment is now being carried out. Currently, with the rapid growth of the nuclear power industry, more and more attention has been paid to nuclear safety in China. Fuel rods with a high standard of quality assurance are crucial to prevent accidental nuclear leakage. It is of significant importance to investigate nuclear fuel rods by neutron radiography. The work described above provides this possibility and gives a primary guideline for investigating actual irradiated fuel rods by neutron radiography at CARR in the future.
Guohai Wei et al. / Physics Procedia 43 ( 2013 ) 307 313 313 Acknowledgements This work was supported by State Key Development Program of Basic Research of China (grant no. 2010CB833106). References [1] E.H. Lehmann, P. Vontobel, A. Hermann. Non-destructive analysis of nuclear fuel by means of thermal and cold neutrons. Nuclear Instruments and Methods in Physics Research A 515 (2003) 745 759. [2] F. Groeschel, P. Schleuniger, A. Hermann, E. Lehmann, L. Wiezel. Neutron radiography of irradiated fuel rod segments at the SINQ: loading, transfer and irradiation concept. Nuclear Instruments and Methods in Physics Research A 424 (1999) 215-220. [3] P. Von Der Hardt, H. Rottger. Neutron Radiography Handbook. D. Reidel Publishing Company, 1981. [4] M Grosse, G Kuehne et al. Quantification of hydrogen uptake of steam-oxidized zirconium alloys by means of neutron radiography. J. Phys.: Condens. Matter 20 (2008) 104263 (7pp). [5] Mo Dawei, Liu Yisi, Jin Guangyu, et al.. Neutron Radiography. Atomic Energy Press,1996(3). [6] Ian S. Anderson, et al.. Neutron Imaging and Applications. Springer SciencetBusiness Media, LLC 2009, p. 69. [7] Post-irradiation Examination Capabilities at the Idaho National Laboratory, available at http://atrnsuf.inl.gov/capabilities/postirradiationexamination/tabid/101/default.aspx [8] Juan J. et al.. Experimental Observations on Fuel Pellet Performance at High Burnup. Journal of Nuclear Science and Technology, Vol. 43, No. 9, p. 1045 1053 (2006). [9] Yuan Luzheng, Shen Feng. Brief Introduction to CARR Status. Proceedings of the International Symposium on Research Reactor and Neutron Science Commemoration of the 10th Anniversary of HANARO-Daejeon, Korea, April 2005, p.35-38. [10] Mitra Ansari, Majid Shahriari. Design of a Nuclear Level Switch using MCNP code, and comparison with experimental results. IEEE NPSS (Toronto), UOIT, Oshawa, ON, 25 & 26 June, 2010 International Workshop on Real Time Measurement, Instrumentation & Control [RTMIC]. [11] Chen Baoshan, Liu Chengxin. Light Water Reactor Nuclear Fuel Element. Chemistry Industry Press,2007.