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It is interesting to notice that for such a low density B4C (70 % TD) the porosity is totally open and consequently 30 % of the B4C column volume could be used to store the helium released. Another point of interest is the tritium retained in the B4C pellets after irradiation. For this purpose measurements of tritium concentration have been performed on B4C fragments. The extraction of tritium is obtained by heating the samples at 1000°C, then the gaseous tritium is converted into tritiated water which is analyzed by scintillation spectrometry.

THORNTON, T. , TULENKO, J. S. Irradiation behavior of PWR Control Materials TRANSAO 39, 1-1076 (1981) 396. [7] DEMARS, R. , DIDEON, C. , THORNTON, T. , TULENKO, J. , PAVINICH, W. , PARDUE, E. B. S. Irradiation Behavior of Pressurized Water Reactor Control Materials Nuclear Technology 62 (1983) 75. , NELSON, J. L Measurement of the Deformability of Austenitic Stainless Steels and NickelBase Alloys in Light Water Reactor Cores Authorized reprint from Standard Technical Publication 1210 Copyright 1993, ASTM.

SANTUCCI, J. Control Rod Materials and Burnable Poisons EPRI NP-1974, Contract TPS 79-708, Final Report, November 1981. [3] HOTT, A. , KELLER, H. , SCHALLENBERGER, J. M. Development of Hafnium and Comparison with Other PWR Control Rod Materials TRANS ANS 39 (1981) 397. 1984- RS 16-517 225/2. 1982- RS 16-513 801/32. [6] DAVIS, H. , DEMARS, R. , DIDEON, C. , THORNTON, T. , TULENKO, J. S. Irradiation behavior of PWR Control Materials TRANSAO 39, 1-1076 (1981) 396. [7] DEMARS, R. , DIDEON, C. , THORNTON, T.

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Advances in Control Assembly Mtls for Water Reactors (IAEA TECDOC-813)


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