2-2

betaeff, a Key Parameter for Controlling Fission Chain Reactions in Nuclear Reactors




Fig. 2-3 Schematic view of FCA, JAERI



Fig. 2-4 Systematic changes of nuclide contributions from 235U, 238U, and 239Pu to betaeff

The value of betaeff is vital for the effective control of the fission chain reaction in a nuclear reactor. This figure shows the nuclide contributions from 235U, 238U, and 239Pu to betaeff in five different cores that were constructed to measure experimental values of betaeff with high accuracy.



Fig. 2-5 Comparison of main contributors to error in betaeff between before and after adjustment

This figure shows a breakdown of prediction errors of betaeff for the five cores and a TCA (Tank-type Critical Assembly) core. After adjustment, betaeff errors are one-half those before adjustment.




Fission neutrons are classified into two groups, (1) the neutrons that appear essentially instantaneously (within 10-14 s) of the fission event and (2) the neutrons that appear with an appreciable time delay from the subsequent decay of radioactive fission products. The former are referred to as prompt neutrons and the latter are called delayed neutrons. Although the fraction of delayed neutrons to fission neutrons is very small (less than 1%), the delayed neutrons are vital for effective control of the fission chain reaction in a nuclear reactor. From the standpoint of nuclear reactor control, it is important to predict accurately the effective delayed neutron fraction, betaeff, especially in innovative light water reactors and fast reactors where a mixture of uranium and plutonium is used as nuclear fuel. To improve the prediction accuracy of betaeff, a program of benchmark experiments was conducted as an international collaboration. It was comprised of experiments at the FCA (Fast Critical Assembly) facility of JAERI (Fig. 2-3) and the MASURCA facility of CEA, France. In these experiments, several core configurations were selected taking into consideration the systematic change of the nuclide contribution from 235U, 238U, and 239Pu to betaeff, as shown in Fig. 2-4. Six organizations from five countries participated in the experiments. Each participant used his own betaeff measurement technique, and the measured results were compared with each other. The individual results have been combined to provide a recommended value having a high accuracy for each core type. Through the analyses of these experiments, delayed neutron data were evaluated and adjusted using current calculation methods. The results show prediction accuracy for betaeff values improved from 3-5% to 2-3%, as seen in Fig. 2-5. These results have been included in the delayed neutron data of the latest evaluated nuclear data library, JENDL-3.3.



Reference
T. Sakurai et al., Adjustment of Total Delayed Neutron Yields of 235U, 238U and 239Pu in JENDL-3.2 Using Benchmark Experiments on Effective Delayed Neutron Fraction betaeff, J. Nucl. Sci. Technol., 39(1), 19 (2002).

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Persistent Quest Research Activities 2002
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