150 INTERNAL DOSE FROM SHORT-LIVED RADIONUCLIDES THE SHORTER-TERM BIOLOGICAL HAZARDS OF A FALLOUT FIELD Therefore, most of the absorbed dose (in ergs/g or rad units) is delivered to the lower large intestine in the case of the radionuclides with relatively long half-lives which are listed in the ICRP Handbook. The material spends 1 hour in the stomach, 4 hours in the small in- were given for 5 different sets of assumptions: ble radioactive material is inhaled with the lung testine, 8 hours in the upper large intestine, and 18 hours in the lower large intestine. Jf radionuclides of shorter half-life are considered in future publications and if MPC values are as the critical body organ; and 5. Insoluble radioactive material is inhaled with various portions of the G.I. tract to become the critical only the lowest maximum permissible values are listed in Table I, The three assumed permissible exposures were 0.3 rem/wk, 15.7 rem/yr or 150 rem/70 years following the exposure, We should note that in Tables I and JI the 0.3 rem/wk is the limiting case-— givenfor single exposure, we may expect other body tissue. In the present ICRP Handbook the assumption is made that the fraction, f,, of the radionuclide passes through the small intestine into the blood so that only (1—f,) reaches the upper and lower large intestine. Therefore, if radionuclides are considered in which f,2x1, the critical organs are unlikely to be the large intestines. Although no official MPC or q values for a short period of single exposure have been agreed upon, unofficial single exposure values have been adopted by some of the laboratories working with certain of the radionuclides in order (o aid in assessing the hazards associated with accidents or “spills.” Previous attempts have been made to prepare tables of MPC values for single exposure. Tables of MPC. values of some 80 radionuclides were given for two cases: 1. The radionuclide is taken into the body by inhalation or ingestion over a portions of the G.I. tract as the critical body organ. The calculations were made for three criteria relative (o permissible exposure and gives the smallest maximum permissible values—with the exception of 5 bone-seeking radionuelides (Sr°+Y®, Sm’, Ra’, natural thorium, and Pu™) in the soluble form. Jn these cases, 150 rem/70 years is the limiting case. In the case of a wound contaminated with insoluble radioactive material it was assumed that all the contamination remained in 1 mg of tissue at the wound site. In the cases of inhalation of radioactive material, the we values given in Tables 1 and IT correspond to the amount of the radionuclides initially present in the air—for example, as the result of an accident—which if inhaled over a period of 24-hour period,‘ and 2. The radionuclide is 8 hours would deliver the indicated dose. The radioactive material decays with a half-life T, over an 8-hourperiod, or by way of a con- tion, and is eliminated with a biological. half- taken into the body by inhalation or ingestion taminated wound. None of these single exposure values hasofficial status. Itis to be expected that single exposure values will be included in the Internal Dose Handhooks in the near future. Table I is a summary of the single exposure data given at the Conference on Peaceful Uses of Atomic Energy in 1955 at Geneva‘. Single exposure values 4 Morgan, K. 2. and M. BR Ford, “Developments im Internal Dose Determinations,” Nucteonica, Vol. 12, Ne 4, $2 Qune 10541, § Morgan, K. 2, W. 8. Snyder, and M. R. Ford, “Maximum Per- migsibla Concentration of Radlonuclides in Air and Water for Short Period Exposure,” International Conference nn the Peaeeful Uses of Atomic Enagy, Geneva, Switzerland(1054). Single Exposure Values for Radionuclides for Tohalation and for Cantaminated Wounds 1. Soluble radioactive material is inhaled; 2. A wound is contaminated with soluble radio- active material; 3. A wound is contaminated with insoluble radioactive material; 4. Insolu- in this period, i. e., both before and after inhalalife T, while in the body. In the case of a wound all the radioactive contamination enters the wound at time zero. Values were not given in the Geneva paper for ingestion because experience had indicated that in cases of single exposure, inhalation in general presents a much greater hazard than ingestion. However, in some accident eases one may be concerned with the ingestion problem and so Table IT is added to give the uc that are considered permissible to ingest in an 8-hour period, Tables I and IT list values of ue present initially at the time of ap accident, e. g., spill, explosion, failure of a iN POSURE Tar. L--MAXIMUM PERMISSIBLE OCCUPATIONAL Ey . Tsotope % w e initially av Se te Ve inhaled during succeerling # 2 (aya 1 4 6 Q n 16 6 7 9 20 1 xi (0.3, TR 2.78108 0.3, BY 4.7X102 0.3, F) a oe Laxn (0.8, L) iH &X107 0.8, 8} a wR 24 a7 (0.3.8) “{Is0 (3, 1) 22KIG CS, BY 1.8, Ky 5 14X16 0.3, L) pace (0.8, K) 26 26 L2xXUE (6.3, Bly 4 (0.3, RN a 28 82X10? 03, La 5.7108 (0.8, Ti) 30 at 1.5100 (0.3, B) .| 22x20? 0.3, B) wi 37 38 38 39 0 a 42 4a Tes, 4.39 X10? (0,3, K} .| £4102 40.3, M) -| 18 @.3, B) | 8 (150, BY 116 (0.3, BY 2 8.3107 (0.3, Fa 32) 44) 46 -} UK (03, K) -| 1 13di0? 2.3, 17X10(0.3, -| 9.83108 (0.8, 4.7X108 (0.8, Rup Rn Rhos, . . Pdsspto%__. 47 a7) 4a) & $2] Agis. ABM. Cc Sn Tein Se 88 56 at, Cats? Rats Bat4-Late. _ 82 a7} 58 a 4 fa 6s a aig Tout La. . BY BY BY K) 1.410 (0.4, K) 2.0x108 (1.3, 5.0310(0.3, 2.0X10? (03, 9.8108 (0.3, 53 ~-| - ~ LI L) L) B) K) 18 3, K) (70 03, B) 0.70 0.3, TY 14X10? 0.3, M) 8? (0.3, B) a8 (0.3, BY 474 (0.3, BY ~( 2.0X 10? (0.3, BY 1 24X10? (150, B) ae OF (0.3, BY | 13X10? (0.3, B) -{ at (0.3, BY * 7) 2axctot (0.3, B) See footnatey at end of tabte, Wound criti Us sue (ue af gh wound) 3) a7 (3) 92 (a, LL (0.8, &) Hraxw-s cos 68 0.31 a 3, LLD 03,1) @A, BY Haus 14 @.3) al 3, LLD 47 wal Ua @a, LL 50X10! (0.4, LLD axle 3) {0 3, A) Wee a7 a 3, Ld 03,8) 3,85 0.3, §) asx(03, K) Lax1@ 0.3, KI 37X12 O38, 1) TEX0.3, BY (a, 03, (0.3, (4,3, (0 3, BD 1A L) 1) 3) 6 3B) 2.2108 (0.3, K) Ww @3,K) 102 (0.3, M) 0.3, BY (1, BD (0.3, BY 3, B) ”@ (0.3, BY 5.9X10+ (0.3, BY 26X10? (0.8, K) Br wa, K BL 0.3, Kp 66 0.38, K> BRO? 0.4, Led 16x16 (0 4, 1) 49 0.3, L) 24xX108 0.2, B) 1a 0.4, Ky a 4.03, Ky 082 0.3, TY 1,1X101 (0.3, My 24 0.3, BY 1a wo, BY 23 0.3, BY 18 03, BY wD (0.3, BY on cc a7 {54° 15K a7) sxc O.3 by G3, 1) 2.8410 10.3, Md $5 27 40 7 during sutceding § (a GBI 10.3) 18X10 # 0.3) 1L6X10°1 @ 31 3 9210-4 (0.31 91 BBX? 1,910! 26X10! 4.8107 ably to be inhaled 26 cu 28X90? (0,3, sk) 26X10(4.3, TRI 94 & GT (raet critical organ (aw mitlaRy avail- AOX1O (0,3) Be S.OX1E 31 V7Xi08 (0.3, TB a (ue indatly evade ahle to be intraled diirig succeed ing hrs} 12x04 (0.8, LLL 442X102 0.3, LUD 14X18 (0.3, LLL) L 7X10(03, 8 MI WB, 8 19 (0.3, LLY LOxlO1 (8, LLN 2.908 (0.3, LEI) 8 (0.3, 8) 4.4102 @.3, TET 1ix<10) 0.4, TH) 20" (0.3, BY BAK(03, F) u Lune eritleal organ tA 1.4XHir4 (08) KI X10-C (0.9) 1 610-8 (0.3) iG msol- able radioact! Toateria) uiitially ay 1.3X106 (0.3, B) .) 28108 3, TB) 53 (0.3, B) 42108 (0.3, sk) 3 7xIU? (0.3, TY 33X10 (0.8, MD B 3, B) 4.3, 8) 8 0.3, 1) 46 (uc of soluble rasdioactive mateial ini tially in wound) ? (3) #2 GYTOor FPL). jer =) Ynhulation | of insoluble rudioactlye material Waourl eont: ‘amination Inhalation | of soluble radigactive material (50, FB) 0.3, BY (0.3, Br 3, Br (0.3, B) 2.3% 10-4 (0.3) BAKM-F ©3) 3) 3) KAKIU3} 4 OXMH4 (0,3) AX10"8 (0.3) 1.4X10~4 (6,3) 7 SXK(0.3) TBXLO~ (0.9) 1,7X20°5 (0.3) 7.5X10-5 (0.9) 6.61075 (0.2) E5X10-8 (0,9) 1L1X10-4 6.3) B.6X10-4 (0.31 16X10~4 (0,3) 1.6% 10-4 (03) 8.5X10-7 (0,3) 16X10-4 49X10-4 19X10-8 1410-5 (3) (0.3) (0.4) (0.4) 5,5X10-# (U3) 6.3X10-T (0.3) Ww (0.8) 27X13 (0.3) 9.01073 (1.3) 31K¢ (09) 21X10(0.3) 4axtus (0g) 3. 2X1-* (0.8) 4.4106 ®@3) 6.3X10-6 (0 3} 4.7X10-* (03) 13X10 ¢ (0.4) 48X10 6 Gay 6.9X10-T (0d) 4,8X 10-6 (0.4) 138XO-§ (0.3) 48X10") 0.31 41X10 @.3) A 7XO-F 0.3) 27X10-* 0.3) D2xte-4 (0.3) 11X1 (0.3) 1.9107 0,37 2,3X107 (0 3) ASX Od) ps] Oe Be 0.3) EBX102 (4 =) 6.7 X10 (0.3) ou a 3) az as) 1424102 (0.9) 8.7X102 (0.3) a a3 &TKIN a] wu 3 3) 3) (0.9) 4) 8) 0.9) cy mR (O,5F (0.3) 7 13 73 & ad s 1.13108 (0.3) $8 3) oF 3) w 23 2 £3 22 3) 03° @3) OB (0.3) 12 (0.3) 43 0.3) ts ae 4 3) 27 oy FOxiot « 33X10? a3 cre 22 av (0.3) (03) (0.3) i (0.3, LL 5.4 03, LLL 86 (0.3, LE 3.9X108 (0.3, LLY 1.310? (0.3, LT v 3, ULI a 3, LLD 0.8) 0.3) 0.3) (0,31 nay (3) 03, ULD 41x10" 0.3, LUT 6 W.3, LIA) ue (6.3, LAA) a4 (wt, LED 1ax1d? 0.3, LLY 9 3, LUD LUCIO (0.9) : 16 46 2 4 27 2% (0.8, LL 3, LD (0.3, LLD (03, LLD 03, LAA) 0.3, LL 1.2109 (0.3, LE) 94 uw 3, LID @3, LL} 13x10 (0.3, LL} 4 (0.3, LIA) 1% 3, LLY &1 @3, LI 2.910? @.3, SI) 22X10" @.3, 91) 7 4, LLG of 3, LLY 66 29° 13 19xi0? YW } 10 (22 ‘98 4, LiL @3, LLL 0.3, LL) (0.8, LLD 3, LED (03, LED (08, Lid) 0 LED