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LWR-PROTEUS Verification of Reaction Rate Distributions in Modern 10 × 10 Boiling Water Reactor Fuel

F. Jatuff, P. Grimm, O. Joneja, M. Murphy, A. Lüthi, R. Seiler, R. Brogli, R. Jacot-Guillarmod, T. Williams, S. Helmersson, R. Chawla

Nuclear Science and Engineering / Volume 139 / Number 3 / November 2001 / Pages 262-272

Technical Paper /

HELIOS, CASMO-4, and MCNP4B calculations of reaction rate distributions in a modern, fresh 10 × 10 boiling water reactor fuel element have been validated using the experimental results of the LWR-PROTEUS Phase I project corresponding to full-density water moderation conditions (core 1B). The reaction rate distributions measured with a special gamma-scanning machine employing twin germanium detectors consisted of total fission Ftot and 238U-capture C8. The average statistical errors for the gamma scans were better than 0.5% for Ftot and 0.9% for C8. The rod-by-rod measurements were performed on 60 different fuel rods selected from the central part of a test zone consisting of actual, fresh SVEA-96+ fuel elements, thus gaining in realism by departing from conventional fuel rod mockups. In the case of Ftot, the root-mean-square (rms) of the rod-by-rod distribution of differences between calculational and experimental (C-E) values has been found to be 1.1% for HELIOS and for CASMO-4, and 1.3% for MCNP4B. For C8, the rms values of the (C-E) distributions are 1.0, 1.3, and 1.4% as obtained with HELIOS, CASMO-4, and MCNP4B, respectively. The effects of using different data libraries (ENDF/B-V, ENDF/B-VI, and JEF-2.2) with MCNP4B were also studied and have been found to be small.

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