Effects of high density dispersion fuel loading on the dynamics of a low enriched uranium fueled material test research reactor |
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| Authors: | Farhan Muhammad Asad Majid |
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| Affiliation: | 1. Chalmers University of Technology, Department of Nuclear Engineering, SE-412 96 Göteborg, Sweden;2. CEA, DEN, Cadarache, DER/SPEx/LDCI, F-13108 Saint-Paul-lez-Durance, France;1. KTH Royal Institute of Technology, Roslagstullsbacken 21, SE-10691 Stockholm, Sweden;2. CEA, DEN, DER, SRJH, CEA Cadarache, 13108 Saint-Paul-lez-Durance Cedex, France;1. KTH Royal Institute of Technology, Roslagstullsbacken 21, SE-10691 Stockholm, Sweden;2. CEA, DEN, DER, SRJH, CEA Cadarache, 13108 Saint-Paul-lez-Durance Cedex, France;1. Physics Department, NRCN, P.O.B 9001, Beer Sheva, Israel;2. CEA, DEN, DER/SPEx, Cadarache, F-13108 St Paul Lez Durance, France;3. The Unit of Nuclear Engineering, Ben-Gurion University of the Negev, Beer-Sheva 84105, Israel;1. Department of Engineering, University of Cambridge, Cambridge CB2 1PZ, UK;2. W. Wilson School of Public and International Affairs, Princeton University, Princeton, NJ, USA;3. Westinghouse Electric Company LLC, Cranberry Township, PA, USA |
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| Abstract: | The effects of using high density low enriched uranium on the dynamics of a material test research reactor were studied. For this purpose, the low density LEU fuel of an MTR was replaced with high density LEU fuels currently being developed under the RERTR program. Since the alloying elements have different properties affecting the reactor in different ways, fuels U–Mo (9w/o) which contain the same elements in same ratio were selected for analysis. Simulations were carried out to determine the reactor performance under reactivity insertion and loss of flow transients. Nuclear reactor analysis code PARET was employed to carry out these calculations. It is observed that during the fast reactivity insertion transient, the maximum reactor power is achieved and the energy released till the power reaches its maximum increases by 45% and 18.5%, respectively, as uranium density increases from 6.57 gU/cm3 to 8.90 gU/cm3. This results in increased maximum temperatures of fuel, clad and coolant outlet, achieved during the transient, by 27.7 K, 19.7 K and 7.9 K, respectively. The time required to reach the peak power decreases. During the slow reactivity insertion transient, the maximum reactor power achieved increases slightly by 0.3% as uranium density increases from 6.57 gU/cm3 to 8.90 gU/cm3 but the energy generated till the power reaches its maximum decreases by 5.7%. The temperatures of fuel, clad and coolant outlet remain almost the same for all types of fuels. During the loss of flow transients, no appreciable difference in the power and temperature profiles was observed and the graph plots overlapped each other. |
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