journal article·2005-08Open access

Thermal hydraulic design and decay heat removal of a solid target for a spallation neutron source

N. Takenaka, D. Nio, Y. Kiyanagi, K. Mishima, M. Kawai, M. Furusaka

Journal of Nuclear Materials· Volume 343· Issue 1-3

Abstract

Abstract Thermal hydraulic design and thermal stress calculations were conducted for a water-cooled solid target irradiated by a MW-class proton beam for a spallation neutron source. Plate type and rod bundle type targets were examined. The thickness of the plate and the diameter of the rod were determined based on the maximum and the wall surface temperature. The thermal stress distributions were calculated by a finite element method (FEM). The neutronics performance of the target is roughly proportional to its average density. The averaged densities of the designed targets were calculated for tungsten plates, tantalum–clad tungsten plates, tungsten rods sheathed by tantalum and Zircaloy and they were compared with mercury density. It was shown that the averaged density was highest for the tungsten plates and was high for the tantalum cladding tungsten plates, the tungsten rods sheathed by tantalum and Zircaloy in order. They were higher than or equal to that of mercury for the 1–2 MW proton beams. Tungsten target without the cladding or the sheath is not practical due to corrosion by water under irradiation condition. Therefore, the tantalum cladding tungsten plate already made successfully by HIP and the sheathed tungsten rod are the candidate of high performance solid targets. The decay heat of each target was calculated. It was low enough low compared to that of ISIS for the target without tantalum but was about four times as high as that of ISIS when the thickness of the tantalum cladding was 0.5 mm. Heat removal methods of the decay heat with tantalum were examined. It was shown that a special cooling system was required for the target exchange when tantalum was used for the target. It was concluded that the tungsten rod target sheathed with stainless steel or Zircaloy was the most reliable from the safety considerations and had similar neutronics performance to that of mercury.
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Research context

OpenAlex topics: Nuclear Physics and Applications · Nuclear reactor physics and engineering · Nuclear Materials and Properties

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References (7)

Show source-provided references
1. Y. Kiyanagi, M. Furusaka, in: Proceeding of the Seventh International Conference Nuclear Engineering, Tokyo, Japan, 19–23 April 1999, ICONE-7231.
2. K. Mishima et al., in: Proceeding of the Fourth Meeting International Collaboration on Advanced Neutron Sources, vol. 1, Utica, USA, 14–19 June 1988, p. 411.
3. N. Takenaka et al., in: Proceeding of the Fourth Meeting International Collaboration on Advanced Neutron Sources, vol. 1, Utica, USA, 14–19 June 1988, p. 424.
4. T. Tanabe, private communication.
5. Leimann · PSI Ann. Rep. · 2002 · 35
6. Baker · Nucl. Instrum. and Meth. A · 1995 · 359 · 45110.1016/0168-9002(94)01735-2 ↗
7. Maloy · Mater. Trans. · 2002 · 43 · 110.2320/matertrans.43.633 ↗