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Standard Test Method for Measuring Neutron Fluence and Average Energy from 3H(d,n) 4He Neutron Generators by Radioactivation Techniques (Includes all amendments And changes 7/12/2022).
Automatically translated name:
Standard Test Method for Measuring Neutron Fluence and Average Energy from 3H(d,n) 4He Neutron Generators by Radioactivation Techniques
STANDARD published on 1.1.2014
Designation standards: ASTM E496-14e1
Note: WITHDRAWN
Publication date standards: 1.1.2014
SKU: NS-46985
The number of pages: 14
Approximate weight : 42 g (0.09 lbs)
Country: American technical standard
Category: Technical standards ASTM
Keywords:
14-MeV, DT, neutron activation, neutron generator, neutron metrology, ICS Number Code 17.240 (Radiation measurements),27.120.30 (Fissile materials and nuclear fuel technology)
Significance and Use | ||||||||||||||||||
5.1 Refer to Practice E261 for a general discussion of the measurement of fast-neutron fluence rates with threshold detectors. 5.2 Refer to Test Method E265 for a general discussion of the measurement of fast-neutron fluence rates by radioactivation of sulfur-32. 5.3 Reactions used for the activity measurements can be chosen to provide a convenient means for determining the absolute fluence rates of 14-MeV neutrons obtained with 3H(d,n)4He neutron generators over a range of irradiation times from seconds to approximately 100 days. High purity threshold sensors referenced in this test method are readily available. 5.4 The neutron-energy spectrum must
be known in order to measure fast-neutron fluence using a single
threshold detector. Neutrons produced by bombarding a tritiated
target with deuterons are commonly referred to as 14-MeV neutrons;
however, they can have a range of energies depending on:
(5.5 Wide variations in neutron
energy are not generally encountered in commercially available
neutron generators of the Cockroft-Walton type. Figs. 1 and 2 (1)6 show the
variation of the zero degree 3H(d,n)4He
neutron production cross section with energy, and clearly indicate
that maximum neutron yield is obtained with deuterons having
energies near the 107 keV resonance. Since most generators are
designed for high yield, the deuteron energy is typically about 200
keV, giving a range of neutron energies from approximately 14 to 15
MeV. The differential center-of-mass cross section is typically
parameterized as a summation of Legendre polynomials. Figs. 3 and 4 (1,2) show how the neutron yield varies
with the emission angle in the laboratory system. The insert in
Fig. 4 shows how the magnitude, A1, of the P1(θ) term, and hence the
asymmetry in the differential cross section grows with increasing
energy of the incident deuteron. The nonrelativistic kinematics
(valid for Ed < 20
MeV) for the 3H(d,n)4He
reaction show that:
5.5.1 Fig. 5 (2) shows how the neutron energy depends upon the angle of scattering in the laboratory coordinate system when the incident deuteron has an energy of 150 keV and is incident on a thick and a thin tritiated target. For thick targets, the incident deuteron loses energy as it penetrates the target and produces neutrons of lower energy. A thick target is defined as a target thick enough to completely stop the incident deuteron. The two curves in 5.6 The Q-value for the primary 3H(d,n)4He reaction is + 17.59 MeV. When the incident deuteron energy exceeds 3.71 MeV and 4.92 MeV, the break-up reactions 3H(d,np) 3H and 3H(d,2n)3He, respectively, become energetically possible. Thus, at high deuteron energies (>3.71 MeV) this reaction is no longer monoenergetic. Monoenergetic neutron beams with energies from about 14.8 to 20.4 MeV can be produced by this reaction at forward laboratory angles 5.7 It is recommended that the dosimetry sensors be fielded in the exact positions where the dosimetry results are wanted. There are a number of factors that can affect the monochromaticity or energy spread of the neutron beam 1.1 This test method covers a general procedure for the measurement of the fast-neutron fluence rate produced by neutron generators utilizing the 3H(d,n) 4He reaction. Neutrons so produced are usually referred to as 14-MeV neutrons, but range in energy depending on a number of factors. This test method does not adequately cover fusion sources where the velocity of the plasma may be an important consideration. 1.2 This test method uses threshold activation reactions to determine the average energy of the neutrons and the neutron fluence at that energy. At least three activities, chosen from an appropriate set of dosimetry reactions, are required to characterize the average energy and fluence. The required activities are typically measured by gamma ray spectroscopy. 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use. |
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2. Referenced Documents | ||||||||||||||||||
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Historical
1.2.2009
Historical
1.6.2009
Historical
1.6.2009
Historical
1.1.2008
Historical
1.2.2011
Historical
1.6.2009
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