JAERI 1287 JNDC Nuclear Data Library of Fission Products Fir

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JAERI1287 1. Introduction A reliable nuclear data library of fission products (FPs) is indispensable for accurate calculation of fission-product accumulation in the nuclear power reactors. It should consist of half-lives, decay schemes, decay energies, neutron reaction cross sections, and fission yields. Accurate knowledge of fission-product accumulation during operation and after shutdown of power reactors is essential to many aspects of nuclear reactor safety, operation, and nuclear safeguard considerations. Certain fission-products are important for accurate reactivity predictions during fuel depletion, conversion, and burnup in nuclear reactor calculations. The decay power of fission products is of great importance in the safety analysis of power reactors. The loss-of-coolant accident (LOCA) is a major current issue today concerning the use of nuclear power. The major defense against a LOCA is the emergency core cooling system (ECCS), and one of the significant constraints on the power rating of a nuclear power reactor is the maximum amount of energy the ECCS can handle. Thus, accurate decay power data are important in evaluating how well the ECCS will work and in calculating the consequences of a LOCA. Decay power also plays an important role in the design of spent-fuel containers and reprocessing facilities. At present the American Nuclear Society Draft Standard ANS 5.1 x) is widely used for the specification of the decay power of fission products for the analysis of a LOCA. The ANS Draft Standard relies upon the work of K. Shure 2) ; of which uncertainties are estimated to be +20%, -40% for the first 10 3 s after shutdown. Since 1973, five new measurements of fission-product decay power were initiated in the United States and Japan to improve the accuracy of fission-product decay power: (a) betaand gamma-ray spectra measurement at Oak Ridge National Laboratory (ORNL) 3 " 6) , (b) a fast response calorimeter measurement at Los Alamos National Laboratory (LANL) 7 ' 8 >, (c) a total absorption or nuclear calorimetric measurement at Intelcom Radiation Technology (IRT) Corporation 9>10) , (d) a second calorimetric measurement using different techniques at the University of California, Berkeley (UCB) n) , and (e) beta- and gamma-ray spectra measurement at the University of Tokyo, Tokai (UTT) 12 " 14) for the fast neutron fission. These experiments were planned mostly to support the safety analysis of the hypothetical LOCA in a light water reactor. These recent accurate measurements enable one the examination of the accuracy of the summation calculation 15>16) of decay power. This calculation is based on solving analytically the large set of ordinary differential equations that describe the production and decay of each nuclide. The summation calculation, having the merit of versatility, can predict the decay power for a mixture of fissionable isotopes with complicated history including the neutron capture transformation of fission products, and can also give detailed isotopic inventories of fission products. The method of summation calculation is essentially exact. However, many of the required nuclear data are imprecisely known. Theoretical or statistical estimations are necessary for half-lives and decay energies of many short-lived nuclides. Therefore, reliability of the fission-product nuclear data library for the summation calculation of decay power should be examined by comparing the summation calculation results with experimental data. There exist several nuclear decay data libraries for the summation calculation of decay power, which include ENDF/B-IV, /B-V, French 17) and English 18 ) files, and Tasaka's librarjesi9,20) y^g 1^^ ones mav be ENDF/B-V and new Tasaka's library 20) . The last one is a
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JAERI 1287 2. Nuclear Data Library
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JAERI1287 133 3. Comparison of Calc
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JAERI 1287 3. Comparison of Calcula
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JAERI 1287 151 4. Calculation of De
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JAERI 1287 4. Calculation of Decay
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JAERI1287 4. Calculation of Decay P
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JAER11287 4. Calculation of Decay P
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JAERI 1287 217 Acknowledgment The a
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