5.2 237Np is available as metal foil, wire, or oxide powder. For further information, see Guide E844. It is usually encapsulated in a suitable container to prevent loss of, and contamination by, the 8201;237Np 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 products 134Cs and 8201;136Cs may be present, which can interfere with the counting of the 0.662 MeV 8201;137Cs-137mBa gamma ray (see Test Methods E320).
5.3.2 140Ba-140La is chosen frequently for short irradiations (see Test Method E393).
5.3.3 95Zr can be counted directly, following chemical separation, or with its daughter 95Nb, using a high-resolution gamma detector system.
5.3.4 144Ce is a high-yield fission product applicable to 2- to 3-year irradiations.
5.4 It is necessary to surround the 237Np monitor with a thermal neutron absorber to minimize fission product production from trace quantities of fissionable nuclides in the 237Np target and from 8201;238Np and 8201;238Pu from (n,γ) reactions in the 8201; 237Np material. Assay of 8201;238Pu and 8201; 239Pu concentration is recommended when a significant contribution is expected.
5.4.1 Fission product production in a light-water reactor by neutron activation products 8201;238Np and 8201; 238Pu has been calculated to be insignificant (1.28201;%), compared to that from 8201;237Np(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 the 8201;237Np is shielded from thermal neutrons (see Fig.8201;2 of Guide E844).
5.4.2 Fission product production from photonuclear reactions, that is, (γ,f) reactions, while negligible near-power and research reactor cores, c......
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ASTM E705-13a Referenced Document
- ASTM E1005 Standard Test Method for Application and Analysis of Radiometric Monitors for Reactor Vessel Surveillance, E 706(IIIA)
- ASTM E1018 Standard Guide for Application of ASTM Evaluated Cross Section Data File, Matrix E 706 (IIB)
- ASTM E170 Standard Terminology Relating to Radiation Measurements and Dosimetry
- ASTM E181 Standard Test Methods for Detector Calibration and Analysis of Radionuclides
- ASTM E261 Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
- ASTM E262 Standard Method for Determining Thermal Neutron Reaction and Fluence Rates by Radioactivation Techniques
- ASTM E320 Test Method for Cesium-137 in Nuclear Fuel Solutions by Radiochemical Analysis
- ASTM E393 Standard Test Method for Measuring Reaction Rates by Analysis of Barium-140 From Fission Dosimeters
- ASTM E704 Standard Test Method for Measuring Reaction Rates by Radioactivation of Uranium-238
- ASTM E844 Standard Guide for Sensor Set Design and Irradiation for Reactor Surveillance, E 706(IIC)
- ASTM E944 Standard Guide for Application of Neutron Spectrum Adjustment Methods in Reactor Surveillance, (IIA)
ASTM E705-13a history
- 2018 ASTM E705-18 Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
- 2013 ASTM E705-13a Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
- 2013 ASTM E705-13 Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
- 2008 ASTM E705-08 Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
- 1996 ASTM E705-96(2002) Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237
- 1996 ASTM E705-96 Standard Test Method for Measuring Reaction Rates by Radioactivation of Neptunium-237