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

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CRITICALITY 663<br />

12.10. The blood plasma from a worker who was overexposed during a criticality accident<br />

had a 24Na specific activity of 37 Bq (0.001 μCi) per mL 15 hours after the<br />

accident. The accidental excursion lasted 10 milliseconds. All the Na in nature<br />

is 23Na. The thermal neutron activation cross section for 2200 m/s neutrons is<br />

0.53 b. What was the absorbed dose due <strong>to</strong> (a) the 14N(n, p) 14C reaction and (b)<br />

the au<strong>to</strong>integral gamma-ray dose due <strong>to</strong> the n,γ reaction on hydrogen?<br />

12.11. (a) For the case where k = 1.0025 and the initial number of neutrons is 1000,<br />

how many neutrons will be present after 10 generations?<br />

(b) After how many generations will the neutron flux be doubled?<br />

12.12. At 20 minutes after a criticality accident the dose rate in a labora<strong>to</strong>ry from the<br />

fission products was 15 Gy/h (1500 rad/h). If the labora<strong>to</strong>ry ventilation system<br />

was shut down at the time of the criticality, how long would it take before a person<br />

could enter the labora<strong>to</strong>ry if his dose equivalent during a projected 15-minute<br />

exposure time is not <strong>to</strong> exceed 50 mGy (5 rads)?<br />

12.13. A transient burst of 1 × 1015 fissions in an unshielded accumulation of fissile<br />

materials causes a <strong>to</strong>tal dose equivalent of 0.25 Sv (25 rems) at a distance of 2 m.<br />

If the neutron-<strong>to</strong>-gamma dose-equivalent ratio is 9 : 1, what were the absorbed<br />

doses from the gammas and from the neutrons?<br />

12.14. The composition, by weight percent, of a concrete mix used in reac<strong>to</strong>r shielding<br />

consists of oxygen, 52.17%; Si, 34.0%; Ca, 4.4%; Al, 3.5%; Na, 1.6%; Fe, 1.5%;<br />

K, 1.3%; and H, 1.0%. The density of the concrete is 2.35 g/cm3 .<br />

(a) Find and tabulate the thermal (2200 m/s) absorption cross section for each<br />

element.<br />

(b) Calculate the linear absorption coefficient (macroscopic cross section) of<br />

the concrete.<br />

12.15. The 131I fission yield is 2.77%. What is the 131I activity in the core of a power<br />

reac<strong>to</strong>r that had been operating at a power level of 3000 MW (t) for<br />

(a) 8 days,<br />

(b) 30 days,<br />

(c) 60 days, and<br />

(d) 180 days?<br />

12.16. Tritium is produced in a nuclear reac<strong>to</strong>r in ternary fission, in which one 3H nucleus<br />

is produced in every 104 fissions. What is the tritium activity in a reac<strong>to</strong>r core that<br />

had been operating at a mean power level of 3000 MW(t) for 2 years?<br />

SUGGESTED READINGS<br />

Ayers, J. A., ed. Decontamination of Nuclear Reac<strong>to</strong>rs and Equipment. Ronald Press, New York, 1970.<br />

Clark, H. K. Handbook of Nuclear Safety. Report No. DP-J32, TID-4500, Office of Technical Services, Washing<strong>to</strong>n,<br />

DC, 1961.<br />

Ethering<strong>to</strong>n, H., ed. Nuclear Engineering Handbook. McGraw Hill, New York, 1958.<br />

Farmer, F. R., ed. Nuclear Reac<strong>to</strong>r Safety. Academic Press, New York, 1977.<br />

Foster, A. R., and Wright, R. L., Jr. Basic Nuclear Engineering, 4th ed. Allyn and Bacon, Bos<strong>to</strong>n, MA, 1983.

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