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Introduction to Health Physics: Fourth Edition - Ruang Baca FMIPA UB

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466 CHAPTER 9<br />

TABLE 9-3. Foil Reactions with Thermal Neutrons<br />

200 m/s<br />

FOIL TARGET TARGET % NUCLEAR PRODUCT PRODUCT ACTIVATION<br />

MATERIAL NUCLEUS ABUNDANCE REACTION NUCLEUS HALF-LIFE CROSS-SECTION (b)<br />

Ag 107 Ag 51.35 n, γ 108 Ag 2.3 min 44<br />

Ag 109 Ag 48.65 n, γ 110 Ag 25 s 110<br />

In 115 In 95.77 n, γ 116m In 54 min 145<br />

U (nat.) 235 U 0.715 n, f F.P. T −1.2 582<br />

Dy 164 Dy 28.18 n, γ 165 Dy 2.32 h 2100<br />

V 51 V 99.76 n, γ 52 52 V 3.77 min 4.5<br />

Mn-Cu 55 Mn 80.00 n, γ 56 Mn 2.56 h 13.4<br />

Cu 63 Cu 69.1 n, γ 64 Cu 12.8 h 4.3<br />

Cu 65 Cu 30.9 n, γ 65 Cu 5.1 min 1.8<br />

Al 27 Al 100 n, γ 28 Al 2.3 min 0.21<br />

Au 197 Au 100 n, γ 198 Au 2.7 days 96<br />

Rh 103 Rh 100 n, γ 104m Rh 4.4 min 12<br />

Rh 103 Rh 100 n, γ 104 Rh 44 s 140<br />

Co 59 Co 100 n, γ 60 Co 5.27 yrs 36.3<br />

NaCl 23 Na 100 n, γ 24 Na 15 h 0.53<br />

Lu-Al 175 Lu 97.5 n, γ 176m Lu 3.7 h 35<br />

B-Al 10 B 19.6 n, α 7 Li Stable 4010<br />

Eu-Al 151 Eu 47.77 n, γ 152 Eu 9.2 h 1400<br />

Pb 208 Pb 52.3 n, γ 209 Pb 3.2 h 6E−5<br />

Nb 93 Nb 100 n, γ 94m Nb 6.6 min 1.0<br />

No adjustment was made for composition of alloys or compounds. This table lists the most useful thermal neutron reactions.<br />

(Courtesy of Reac<strong>to</strong>r Experiments, Inc.)<br />

are calibrated by exposing the pack <strong>to</strong> a known beam of neutrons and then measuring<br />

the induced activity. (A thermoluminescent dosimeter may be added <strong>to</strong> measure the<br />

gamma-ray exposure from a criticality accident.)<br />

Neutron Counting with a Proportional Counter<br />

Counting in the proportional region makes it simple <strong>to</strong> measure neutrons in the<br />

presence of gamma radiation. A neutron counter used for this purpose uses BF3 gas<br />

<strong>to</strong> take advantage of the n, α reaction on 10 B:<br />

10 B(n,α) 7 Li.<br />

Boron-10 has a high cross section for this reaction, 4010 barns for thermal neutrons,<br />

and consequently makes a very sensitive detecting medium. The alpha particles<br />

resulting from this reaction are produced inside the detec<strong>to</strong>r. Because of the great<br />

difference between the output pulses resulting from the alpha particles and Li ions<br />

and those due <strong>to</strong> gamma rays, it is a simple matter <strong>to</strong> discriminate electronically<br />

against all pulses except those due <strong>to</strong> the alphas and Li ions when a neutron is<br />

captured by 10 B.<br />

The sensitivity of a BF3 neutron detec<strong>to</strong>r may be increased by using 10 B-enriched<br />

BF3 gas. Naturally occurring boron contains about 19.8% 10 B. However, it is possible<br />

<strong>to</strong> concentrate the 10 B iso<strong>to</strong>pe <strong>to</strong> the extent that BF3 gas containing 96% 10 Bis<br />

routinely available from commercial suppliers. The BF3-filled counter is a sensitive<br />

and simple thermal-neutron detec<strong>to</strong>r and is widely used by health physicists for<br />

measuring thermal-neutron flux. Furthermore, since 680 thermal neutrons/cm 2 /s

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