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17-Phys-B1 Radiation Physics · May 2016

Question 2 of 7: Mixed-Field Equivalent Dose from Neutron and Gamma Exposure

Nivaar worked solution (AI-drafted; not reviewed by a licensed engineer)

Notes on this paper

Paper format. 98-Phys-B1 Radiation Physics, National Examination May 2016 — a three-hour open-book examination in which any non-communicating calculator is permitted (the candidate must record the calculator's make and model on the first sheet). The cover page states the exam has 7 questions worth a total of 89 points, of which only 80 points' worth need be answered for full marks; every question and sub-part is nonetheless answered in full below so the paper remains a complete study resource. The cover page's own marking-scheme summary (12+5+10+6+16+20+20 = 89) is internally consistent with the stated total. The cover page also invites the candidate to submit a written statement of any assumptions made where a question is open to interpretation — this licence is used below in Question 2 (the source unit "pGy" is used literally though it is almost certainly a truncated "mGy"/ "μGy"; the ratio of contributions, which is what the question asks for, is unit-independent), Question 5(b) (the fission-energy-distribution percentages are illustrative textbook values, since the source gives no numeric data to compute them from), and Question 6 (the "dots" in the count-rate table are filled in via Poisson counting statistics and the stated variance combination rule).

Reference texts. K. S. Krane, Introductory Nuclear Physics (nuclear reaction equations, fission energetics, mass–energy conservation); F. H. Attix, Introduction to Radiological Physics and Radiation Dosimetry (photon interactions, pair production, attenuation); J. R. Cember and T. E. Johnson, Introduction to Health Physics, 5th ed. (internal dosimetry, radiation weighting factors, ALARA/protection tenets, counting statistics); J. E. Turner, Atoms, Radiation, and Radiation Protection, 3rd ed. (tritium hazards, neutron interactions, non-ionizing vs. ionizing radiation).

Question 2: Mixed-Field Equivalent Dose from Neutron and Gamma Exposure (5 marks)

Question text not reproduced: the examination questions are © Engineers and Geoscientists BC. Open the official past paper (linked at the top of this page) to read the question, then follow the worked solution below.

Given. Absorbed doses from three field components over a 3-month period, in the source's own units.

Given data
Field componentAbsorbed dose $D$Radiation weighting factor $w_R$
Thermal neutrons50 (source units)5 (ICRP-60, $E<10$ keV)
Fast neutrons ($<2$ MeV)2020 (ICRP-60, 100 keV–2 MeV peak)
Gamma rays1001

Find. (a) the total biological (equivalent) dose $H=\sum w_R D_R$; (b) which component dominates the equivalent dose and is therefore the best target for dose reduction.

Approach. Apply the ICRP radiation weighting factor $w_R$ appropriate to each field's energy (thermal neutrons sit in the lowest-$w_R$ neutron bracket; fast neutrons below 2 MeV sit in the highest, $w_R=20$, bracket; photons always carry $w_R=1$), sum the per-component equivalent doses, then compare their individual shares of the total.

  1. Part (a) — equivalent dose from each component. $$H_R = w_R \times D_R$$ $$\boxed{H_{\text{thermal}} = 5\times50 = 250,\quad H_{\text{fast}} = 20\times20 = 400,\quad H_{\gamma} = 1\times100 = 100 \ \ (\text{source-unit equivalent dose})}$$ $$\boxed{H_{\text{total}} = 250+400+100 = 750\ (\text{source-unit equivalent dose})}$$
  2. Part (b) — which component to target. Despite having the smallest absorbed dose of the three (20 vs. 50 and 100), the fast-neutron component carries the largest equivalent dose (400 of 750, or 53%) because its weighting factor ($w_R=20$) is four times the thermal-neutron value and twenty times the gamma value — fast neutrons in the 100 keV–2 MeV range are the most biologically damaging radiation per unit absorbed energy of any of the three. Reducing the fast-neutron field (e.g. additional hydrogenous moderation/shielding near the source) therefore yields the largest reduction in total equivalent dose per unit of absorbed-dose reduction achieved — more effective than an equal effort spent on the gamma or thermal-neutron components.

Check: the source prints the absorbed doses in "pGy" (picogray); at that magnitude ($10^{-12}$ Gy) none of these exposures would be measurable over a 3-month monitoring period, so the intended unit is almost certainly "mGy" or "μGy" (both plausible occupational-monitoring scales). The comparison in part (b) is a ratio of $w_R D_R$ products and is therefore unaffected by which absolute unit is intended; the numbers are used literally as printed, per the exam's own invitation to state assumptions.

Question 2 — results
QuantityValue
(a) $H_{\text{thermal}}$250 (source-unit equiv. dose)
(a) $H_{\text{fast}}$400
(a) $H_{\gamma}$100
(a) $H_{\text{total}}$750
(b) Target for reductionfast neutrons (53% of total equivalent dose)