5.1 Refer to Practice E261 for a general discussion of the determination of fast-neutron fluence rate with fission detectors.
5.2 238U is available as metal foil, wire, or oxide powder (see Guide E844). It is usually encapsulated in a suitable container to prevent loss of, and contamination by, the8201;238U and its fission products.
5.3 One or more fission products can be assayed. Pertinent data for relevant fission products are given in Table 1 and Table 2.
5.3.1 137Cs-137mBa is chosen frequently for long irradiations. Radioactive products8201;134Cs and8201;136Cs may be present, which can interfere with the counting of the 0.662 MeV8201; 137Cs-137mBa gamma rays (see Test Methods E320).
5.3.2 140Ba-140La is chosen frequently for short irradiations (see Test Method E393).
5.4 It is necessary to surround the8201;238U monitor with a thermal neutron absorber to minimize fission product production from a quantity of8201;235U in the8201;238U target and from8201; 239Pu from (n,γ) reactions in the8201;238U material. Assay of the8201;239Pu concentration when a significant contribution is expected.
5.4.1 Fission product production in a light-water reactor by neutron activation product8201;239Pu has been calculated to be insignificant (lt;28201;%), compared to that from8201;238U(n,f), for an irradiation period of 12 years at a fast-neutron (E gt; 1 MeV) fluence rate of 18201;×8201;1011 cm−2 · s−1 provided the8201;238U is shielded from thermal neutrons (see Fig. 2 of Guide E844).
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