TWI317023B - Measurement and calibration method of volume source calibration phantom - Google Patents
Measurement and calibration method of volume source calibration phantom Download PDFInfo
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- TWI317023B TWI317023B TW95138162A TW95138162A TWI317023B TW I317023 B TWI317023 B TW I317023B TW 95138162 A TW95138162 A TW 95138162A TW 95138162 A TW95138162 A TW 95138162A TW I317023 B TWI317023 B TW I317023B
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Description
1317023 九、發明說明: 【發明所屬之技術領域】 本發明係有關一種校正假體與校正方法,尤其^ 直接使用各種不同密度之體射源校正假體來取得種 效率的校正曲線’依據待測核廢棄物樣品之密^ 測 體射源校正假體的計測效率,可量測不同物夕密度 之總加馬活度或比活度,獲得準確量測的結果之二物樣品 校正假體及其量測與校正方法。 種體射源 【先前技術】 至目前為止,對極低活度體積核廢棄物之總 度量測之儀器為大面積塑膠閃燦體偵檢 ^二=射a …。r),其優點為輻 量樣=間短、廢棄物容積不限制及输 缺點不=用之廢棄物活度監測器之其校正方法卻具有下列 、”’占_ ( 1 )活度量測低估或高仕,、g # μ &上 同廢辛物讀考慮重量而忽略不 效^校正^ 度,所造缝射自吸收效應⑺計測 立密“一般使用早-物質在監測器的屏蔽體中建 符:略樣品非單一物質組成⑺樣品量測位置不 置,鱼改^測樣品時—律將樣品放置在屏蔽體内下方位 —般不限時之胁…讀置有誤⑷樣雜積不符合, 器距離不—勤=體積大t ’與效率校正時距各侧爍制 安全管理H讀丨析4差;因此無法滿足輻射防護 ’于廢棄物活度分析的精雄性要求。⑸沒有修正 1317023 ,菜,樣品中各種核種之輕射能量及多核種時 算,造成的總活度量測誤差。 又 來研究人*更進—步發展可取代原有在活度監測器 空間點射源效率之校正方法,執行核廢棄物加馬 、·χ>" X之^’作為判斷核廢棄物與—般無歸廢棄物的分 類作業,目前塑膠閃爍偵檢器的效率校正方法是⑴美國 Th圓-Eberllne公司使用穿透因子(tr_issiQn facto) 來修正不同標準質量自吸收效應,公式為TF=屏蔽射源之淨計 數/無屏敝射源之淨計數,其—般的,當作補償空 氣中無屏蔽射源在幾何中心的校正效率,在效率校正標將建 立完成的水假體校正效率内的穿透因子參數設定為i,並在質 量參數(每10kg I-單位)輸入重量;則待測之不同材料的 樣品重量會相對已奴穿賴子為丨的重量,㈣修正後的 樣品加馬總活度;⑵德國R娜公司之使用單一物質鐵板組 成的多密度校正效率;⑶日本(japan Nuclear Energy Saf奶1317023 IX. Description of the invention: [Technical field of the invention] The present invention relates to a method for correcting a prosthesis and a correction method, in particular, directly using a body source source of various densities to correct a prosthesis to obtain a calibration curve of the species efficiency. The density of the nuclear waste sample is used to correct the measurement efficiency of the prosthesis, and the total activity or specific activity of the different density of the object can be measured, and the two samples of the accurate measurement result can be used to correct the prosthesis and Its measurement and correction methods. Seed source [Prior Art] Up to now, the instrument for measuring the total activity of very low activity volume nuclear waste is a large area plastic flash detection. r), the advantages are the spoke sample = short, the waste volume is not limited, and the shortcomings of the loss are not = the use of the waste activity monitor has the following correction method, "% _ (1) live measurement Underestimation or high-profile, g # μ & on the same waste physics reading to consider the weight and neglect the ineffective ^ correction ^ degree, the seam produced by the self-absorption effect (7) measured vertical density "usually use early - substance shielding in the monitor In-body construction: a slight sample is not a single substance composition (7) the sample measurement position is not set, when the fish is changed to test the sample - the law is placed in the shield body under the direction of the general-purpose threat... read misplaced (4) sample Non-conformity, device distance is not - diligence = large volume t ' and efficiency correction time from each side of the fire safety management H reading analysis 4 difference; therefore can not meet the radiation protection 'in the male activity requirements of waste activity analysis. (5) There is no correction for the total live measurement error caused by the light energy and multi-nuclear time of various nuclear species in 1317023, vegetables and samples. In addition, the researcher* is more advanced and can replace the original method of correcting the source efficiency of the activity monitor. The implementation of nuclear waste plus horse, χ>" X^^' is used to judge nuclear waste and As for the classification of waste without waste, the current efficiency correction method for plastic scintillation detectors is (1) US Th circle-Eberllne uses the penetration factor (tr_issiQn facto) to correct the different standard mass self-absorption effects. The formula is TF = shielded shot. The net count of the source/net count of the no-screen source, which is generally used as compensation for the correction efficiency of the unshielded source in the geometric center of the air, within the efficiency of the water prosthesis correction that the efficiency calibration target will be established. The penetration factor parameter is set to i, and the weight is input in the quality parameter (every 10kg I-unit); then the sample weight of the different materials to be tested will be relative to the weight of the slaves who have been used as slaves. (4) The corrected sample is added to the total Activity; (2) multi-density correction efficiency of German Rna company using single substance iron plate; (3) Japan (japan Nuclear Energy Saf milk)
Organization)之金屬管及金屬板組成的多核種校正效率;(4) 美國NE Technology公司使用多核種點射源及單一物質巴西 原木(密度為1)組成的多重量(〇〜60Kg)的校正效率。但是目 前廣泛使㈣這些修正方法減僅考慮大_重量及幾何形 狀’但疋&有充分修正樣品之物質質量自吸收效應及各種物 質與能量反應的因素’無法得到樣品正確的加馬總活度。 綜合上述,因此亟需一種體射源校正假體及其量測與校 正方法來解決習用技術所產生之問題。 【發明内容】 7 1317023 測盘ΪΓΓΓΓ目的是提供—種體射源校正假體及其量 取得穷戶盘==利用各種不同密度之體射源校正假體來 密产對二、;;二的校正曲線’依據待測核廢棄物樣品之 新^^夕'山度體射源校正假體的計测效率,可量測不同物 貝核廢棄物樣品之細加 、同物 果之目的。U馬活度或比活度,達到準確量测的結 ί發明的第二項目的是提供—種體射源校正假f及JL曰 各種加馬輻魏量之活度修正使用之目的。 為樣叩之 測與提供—種體射源校正假體及其量 得準確活度之目Γ 效率分析樣品活度,達到獲 t了達到上述之目的,本發明提供 内,該監之:有= 校正假體包複度無15 =體“ 以及至少-射源板體,其係係堆®於该容器内; 板體係與該複數個板體堆叠於該固射源’該至少-射源 板。較佳的是,該《可為—金ς料1金屬材料為―鐵 較佳的是,乾板體可為—非 選擇為紙板、木板、石膏、堡克 ;'。该非金屬材料可 者。 、橡皮以及玻璃其中之— 較佳的是,該射源為-r射源。其[,該順可選 1317023 請參閱圖一所示,該圖係為廢棄物活度監測器與體射源 ' 校正假體示意圖。該廢棄物活度監測器丨,其係具有相同厚度 鉛組合之六面立方之一屏蔽體10,該屏蔽體10内具有—檢測 空間100,在該檢測空間100内之壁面上具有六部相同大面積 之輻射活度偵檢器11,在本實施例中,該輻射活度偵檢器U 係為塑膠閃爍體偵檢器。該檢測空間100内設置有重量計, 可量測待測物之重量。該活度監測器更具有微電腦處理器 12,利用微電腦内藏計算程式軟體與校測參數,可計讀樣品 鲁 及背景的輻射總活度(Bq)或比活度(Bq/g)、效率校正及儀 器最小可測活度等功能,並可列印及顯示分析結果。 、 在該檢測空間100内具有為均勻活度之一體射源校正假 ' 體2。請芩閱圖一 A所示,該體射源校正假體2之外圍為一制 式谷态20,§亥制式谷器20内具有一内部空間21。請參閱圖 二B所示,該圖係為板體與射源板體堆疊示意圖。該内部空 間21内可以堆疊複數枚均勻材質之板體22以及射源板體 23。該板體22之材質可為金屬材料或者是非金屬材料。該金 屬材料選擇為鐵板;該非金屬材料則為紙板、木板、石膏、 壓克力、橡皮、玻璃。 在本實施例中係將將七種不同材料切割成每塊長33cm寬 33cm及厚lcm的大面積均勻規格材料,再分別將每塊材料重 . 叠組成與樣品制式容器尺寸相近之長33cm寬33cm及高30cm …的均勻校正假體’重量範圍在5 kg〜1〇〇 kg,其材料重量相 對容積(33αη3)得到校正假體之平均密度,而由紙板(密度 0. 15gon 3)、木板(密度 〇. 55gcm 3)、石膏(密度 〇. 75gcm 3)、 壓克力(密度1.13gcm3)、橡皮(密度18〇gcm3)、玻璃(密 1317023 度2.咖〇及鐵板(密度3)組成各種密度的校正假體。 在七種密度的個別校正假體中’分別放置對稱相等間隔 的七片大面積之該射源板體。請參閱圖三A所示,該圖係為 本發明^射源板體較佳實施例剖面示意圖。該射源板體烈、具 有一上複貝層23G、-射源層23卜—防漏濾紙層您以及一 下護貝層233。該防漏濾紙層挪,其係形成於該下護貝層挪 上’遠射源層231則形成於該防漏濾紙層232上,該射源層 231具有複數個射源,該上護貝層23〇,其係形成於該防漏渡 紙層32上,該上護貝層23〇與該下護貝層2犯可提供保護 該射源層23卜 八’ :玄射源為一 7射源。其中該7射源可選擇為„鈷、,37 絶、、Μ、及其組成其中之―者。接下來說明形成該複數 個射,之方法’請參閱圖三Β所示,在該防漏濾紙層232上 均勻刀」成36點,母點均勻滴入〇. 2CC液體射源2310共36 滴,其每一滴射源2310約擴散成低於直徑5cm之圓圈,每個 圓圈相鄰但不重叠的核種。57Co、l37Cs、54Mn及6°Co的各七片 大面積射源的總活度分別為58 kBg、72 kBg及90 kBg。透過 4個核種Co、Cs、54Mn及6°Co,共可以組成4個不同能量 及刖述之七種不同密度的均勻活度之體射源校正假體。 請參閱圖四所示,該圖係為本發明量測與校正方法較佳 實施例示意圖。其步驟為: (1)岔度與計測效率校正 ――該校正方法3其步驟如下,首先進行步驟30使用一組固 疋谷積之多核種大面積表面射源與7種密度組成的體射源校 正饭肢,包含廣範圍的能量及密度。接著進行步驟31,在監 1317023 心的幾何位置得顺度與剌財㈣的校正曲 (2)光子能量依持性 ft不同加馬能量相ns能量的比值差異,在廢 债檢益之幾何中心、,分別放置大面積加馬射源%。(能= 1^136_、_ 662 _、5%1(能量 834 _、 5及Co/能量1173㈣和1332 keV)計測,得到加馬核種Organization) The multi-nuclear calibration efficiency of metal tubes and metal plates; (4) US Technology Corporation uses multi-core seed source and single material Brazilian logs (density 1) to determine the multi-weight (〇~60Kg) correction efficiency. However, at present, (4) these correction methods are widely reduced to consider only large _ weight and geometry 'but 疋 & have sufficient correction of the material mass self-absorption effect of the sample and the reaction of various substances with energy' can not get the correct sample of the horse degree. In summary, there is a need for a body source calibration prosthesis and its measurement and correction methods to solve the problems associated with conventional techniques. [Summary of the Invention] 7 1317023 The purpose of the test is to provide a seed source correction prosthesis and its quantity to obtain the poor disk == use a variety of different density of the body source to correct the prosthesis to close the production of the second; The calibration curve 'measures the measurement efficiency of the new ^^ ' ' mountain body source correction prosthesis according to the nuclear waste sample to be tested, and can measure the fine addition and the same fruit of the sample of different nuclear samples. U-horse activity or specific activity, to achieve accurate measurement of the knot. The second project of the invention is to provide the purpose of correcting the activity of the various types of artificially-corrected false f and JL. For the measurement and provision of the sample - the source of the source correction of the prosthesis and the accuracy of its measurement of the efficiency of the analysis of the sample activity, to achieve the above purpose, the present invention provides, the supervision: there = Correction of the prosthesis package without 15 = body "and at least - the source plate body, the system stack ® in the container; the plate system and the plurality of plates stacked on the solid source" the at least - source Preferably, the "metal material" is "iron", preferably the dry plate body can be - non-selected as cardboard, wood, gypsum, fort; Among them, the rubber and the glass - preferably, the source is a -r source. [, the optional 1317023, please refer to Figure 1, the waste activity monitor and body The source 'correction prosthesis diagram. The waste activity monitor 丨 is a six-sided cubic shield 10 having the same thickness lead combination, and the shield 10 has a detection space 100 in the detection space 100. There are six radiation active detectors 11 of the same large area on the inner wall surface. In this embodiment, the spokes The activity detector U is a plastic scintillation detector. The detection space 100 is provided with a weight meter for measuring the weight of the object to be tested. The activity monitor further has a microcomputer processor 12, which utilizes the microcomputer. The library software and calibration parameters can be used to read the total activity (Bq) or specific activity (Bq/g) of the sample and background, the efficiency calibration and the minimum measurable activity of the instrument, and can be printed. And displaying the analysis result. In the detection space 100, there is a body source for the uniform activity to correct the false body 2. As shown in FIG. 1A, the periphery of the body source correction prosthesis 2 is a standard valley. In the state 20, the internal system 20 has an internal space 21. Referring to Figure 2B, the figure is a stack of the plate body and the source plate. The inner space 21 can be stacked with a plurality of uniform materials. The plate body 22 and the source plate body 23. The material of the plate body 22 may be a metal material or a non-metal material. The metal material is selected as an iron plate; the non-metal material is cardboard, wood board, gypsum, acrylic, rubber, Glass. In this embodiment, there will be seven kinds of The material is cut into a large area uniform material with a length of 33cm, a width of 33cm and a thickness of lcm, and each material is re-stacked to form a uniform corrected prosthesis with a length of 33cm, a width of 33cm and a height of 30cm, which is similar to the size of the sample preparation container. The weight ranges from 5 kg to 1 〇〇kg, and the relative weight of the material weight (33αη3) gives the average density of the corrected prosthesis, and the paperboard (density of 0.15 gon 3), wood board (density 〇 55gcm 3 ), gypsum (density) 75 75gcm 3), acrylic (density 1.13gcm3), rubber (density 18〇gcm3), glass (density 1317023 degrees 2. curry and iron plate (density 3) to form a calibration prosthesis of various densities. In the seven density individual correction prostheses, seven large-area of the source plates are symmetrically equally spaced. Please refer to FIG. 3A, which is a cross-sectional view of a preferred embodiment of the present invention. The source plate body is strong, has a top layer of 23B, a source layer 23, a leak-proof filter paper layer, and a protective layer 233. The leakage filter paper layer is formed on the lower shell layer. The long-range source layer 231 is formed on the leak-proof filter paper layer 232. The source layer 231 has a plurality of emitters. a layer 23〇 formed on the leakage preventing paper layer 32, the upper shell layer 23〇 and the lower shell layer 2 are provided to provide protection for the source layer 23 八八': the source is a 7 Source. The 7-ray source can be selected as „Cobalt, 37 、, Μ, and its constituents. Next, the method of forming the plurality of shots is described, please refer to Figure 3Β, in the leakage prevention. The filter paper layer 232 is evenly cut into 36 points, and the mother point is evenly dropped into the crucible. The 2CC liquid source 2310 has a total of 36 drops, and each drop source 2310 is diffused into a circle of less than 5 cm in diameter, and each circle is adjacent but not Overlapping nuclear species. The total activity of each of the seven large-area sources of 57Co, l37Cs, 54Mn and 6°Co were 58 kBg, 72 kBg and 90 kBg, respectively. Through four nuclear species Co, Cs, 54Mn and 6°Co, a total of four different energy and seven different densities of uniform density of the body source corrected prosthesis can be formed. Please refer to FIG. 4, which is a schematic diagram of a preferred embodiment of the measurement and correction method of the present invention. The steps are as follows: (1) 岔 degree and measurement efficiency correction - the calibration method 3 has the following steps: First, step 30 is performed using a set of multi-nuclear large-area surface source and solid density of 7 kinds of density. The source corrects the rice limb and contains a wide range of energy and density. Then proceed to step 31, in the geometric position of the 1317023 heart, and the correction of the (4) photon energy dependence ft energy plus the energy phase ns energy difference, in the geometric center of the waste debt detection ,, respectively, to place a large area plus the source of the horse. (Can = 1^136_, _ 662 _, 5%1 (energy 834 _, 5 and Co / energy 1173 (four) and 1332 keV) measurement, get the horse nuclear
C〇 H及137Cs之核種計測效率,再除以各別核種之 能量分支比(¾為96 %、137CS為85 %、為1〇〇 %及% 為200 %),得到加馬核種57C〇、54Mn、6°Co及l37cs在不同平 均密度時,其能量與光子偵測效率如圖七所示,顯示光子偵 測政率忐量遞增而遞增,在高能量時密度的變化對光子偵 測效率影響大,相反的在低能量時密度的變化對光子偵測效 率景^響較小;另外,不同密度的光子能量57C〇 、54Mn、6QC◦相 對Cs之偵測效率比如表1,作為樣品非單一核種之加馬總 活度計算用。 一The nuclear species measurement efficiency of C〇H and 137Cs is divided by the energy branch ratio of each nuclear species (96% for 3⁄4, 85% for 137CS, 1% for % and 200% for %), and 57C is obtained. The energy and photon detection efficiency of 54Mn, 6°Co and l37cs at different average densities are shown in Figure 7. It shows that the photon detection rate increases and increases, and the density changes to photon detection efficiency at high energy. The influence is large. On the contrary, the change of density at low energy has a small response to photon detection efficiency. In addition, the detection efficiency of photon energy of different densities 57C〇, 54Mn, 6QC◦ relative to Cs is shown in Table 1, as sample non- The total activity of the single nuclear species is calculated. One
表1、 ----- 廣多m里光子能量偵測效率比 密度 57Co / 137Cs Cg/cm3) 54Mn / 137Cs 60C〇 / 137C 0.15 0.40 1. 25 1.49 0.5 0.32 1.18 1.44 0.75 0. 26 1. 13 1.41 1.13 0. 23 1.01 1.30 1.8 0. 17 0.79 1. 11 2.5 0. 16 0. 77 0. 99 3.0 0.08 0.63 0.85 1317023 (3) 樣品量測 然後進行步驟32,將一廢棄物样^ & 體容積相同的制式容器内以形成—檢:、f與體射源校正假 驟33,利用監測器碎稱該檢測樣品之重旦°°炊=下來進行步 ?品之密度(重量/嫌然後對應該:正=:= 叩之對應加馬總活度。最後進彳了步驟%,再㈣冑门 •=(相對^核種能量)及多核種時加馬總活度的 修正後,可獲得正確的加馬總活度。 Τι△式 (4) 、驗證分析 整箱活度量測的儀器需要有正確的加馬總活度計管方 .法,㈣合難活度紐之要求,料紐證#:Table 1. ----- Guangduo Miri photon energy detection efficiency ratio density 57Co / 137Cs Cg/cm3) 54Mn / 137Cs 60C〇 / 137C 0.15 0.40 1. 25 1.49 0.5 0.32 1.18 1.44 0.75 0. 26 1. 13 1.41 1.13 0. 23 1.01 1.30 1.8 0. 17 0.79 1. 11 2.5 0. 16 0. 77 0. 99 3.0 0.08 0.63 0.85 1317023 (3) Sample measurement then proceed to step 32 to treat a waste sample & The same volume of the standard container to form - check:, f and body source correction false step 33, using the monitor to break the weight of the test sample ° ° ° = down to the density of the product (weight / suspect and then Should: Positive =:= 叩 corresponds to the total activity of the horse. Finally, the step %, and then (4) 胄men•=(relative to the nuclear energy) and the multi-nuclear gamma total activity correction, you can get the correct The total activity of the gamma. Τι△ type (4), verification analysis of the whole box live measurement instrument needs to have the correct total activity of the gamma meter. Method, (four) the requirements of the difficulty of activity, the New Zealand certificate#:
為多核種時(主要為1n,c〇),其個別核種 分析結果,其準確性的差異是否在可接受範圍内。 X (4.1)最低可測活度(MDA) • 美國核能管制委員會之NUREG-1507(1998)的最低可 測活度之計算公式如下: jW; ext MDy4 = 3 + 4.65 其中:(偵檢器限度,95〇/〇可信賴度)For multinuclear species (mainly 1n, c〇), the accuracy of the individual nuclear species analysis results is within the acceptable range. X (4.1) Minimum measurable activity (MDA) • The minimum measurable activity of the US Nuclear Regulatory Commission's NUREG-1507 (1998) is calculated as follows: jW; ext MDy4 = 3 + 4.65 where: (detector limit , 95〇/〇 trustworthiness)
Cm .背景計數率(CpS) f:核種計測效率 t:計測時間(sec)Cm. Background count rate (CpS) f: Nuclear measurement efficiency t: Measurement time (sec)
虽平均背景計數為1500,由本監測器Eberline WCM-10PC 計算2分鐘各種平均密度的5ΐ〇、54Mn、⑶以及最低可測 1317023 活f結果如表2及圖五所示,在各種相同密度時仙⑺及⑶以 的最低可測活度有—致性的數值,當平均密度在丨g/cm3〜2 g/cm日守的Co及37cs其—a值最小;當平均密度<;lg/cm3及 >2 g3/cm3時的6°Co及I37Cs其MDA值皆略高於1 g/cm3〜2 g/cf 之 MDA 值的 2 倍,約為 0.003 Bq/g&〇.〇1〇Bq/g,sAlthough the average background count is 1500, the results of the average average density of 5ΐ〇, 54Mn, (3) and the lowest measurable 1317023 calculated by Eberline WCM-10PC for 2 minutes are shown in Table 2 and Figure 5. (7) and (3) The lowest measurable activity has a value of the same, when the average density is 丨g/cm3~2 g/cm, the Co and 37cs have the lowest value of -a; when the average density is <;lg/ The MDA values of 6°Co and I37Cs at cm3 and >2 g3/cm3 are slightly higher than 2 times of the MDA value of 1 g/cm3~2 g/cf, which is about 0.003 Bq/g&〇.〇1〇 Bq/g,s
要疋重i率的變化為線性趨勢,而核種幾何中心效率的變化 為才a數趨勢,因此當重量太輕或太重時,效率的變化大於重 量’在各種相同密度時6QC〇的MDA,皆低於l37Cs。The change in the i-rate is a linear trend, and the change in the efficiency of the nuclear geometric center is the trend of the a number. Therefore, when the weight is too light or too heavy, the change in efficiency is greater than the weight of the MDA at 6QC〇 at various same densities. All are lower than l37Cs.
Mn、6°Co及I37CS之最大的最低可測活度分別為〇. 〇〇9Bq /g、0. 001 Bq /g 及 〇. 〇1〇 Bq /g,54Mn 與 mCs 能量較接近其各 種岔度材質如布料、水、鐵管及鋼筋之肋A皆極相似。另外, Mn、Co及137Cs之最低可測活度(Bq/g),皆能符合主管機關 對解除管制之外釋限值,其量測儀器最低可測活度需低於國 際原子能總署IAEA規範之核種導出限值(如54Mn、%〇及137Cs 為0. lBq/g)之1〇倍的要求。另外,參考美國Antech公司型 式3300-200之清潔廢棄物監測器操作手冊,其量測2分鐘背 景的6QCo及137Cs之儀器最低可測活度分別為〇. 〇〇9 Bq /g及 0. 015 Bq/g’與本研究活度監測器之儀器最低可測活度相似。 另外’觀察本塑膠閃鑠體偵檢器的空間最低可測活度(MDA) 與日ττ間的關係’當s十測時間各為lmin、2 min、5 min、8 min 及10 min時,其6GCo及l37Cs之最低可測活度(如)的變化如 圖六所示’當計測時間由lmin延長至5 min時其60C〇及137Cs 之最低可測活度’分別降低1. 9倍及2. 0倍;而計測時間由 1 min延長至1 〇 min時其6GCo及137Cs之最低可測活度,分別 降低2.5倍及2.7倍,在8 111丨11延長至1〇111丨11時其6()(^〇及137匚5 1317023 之最低可測活度亦變化不大,僅分別降低9 %及15 %。 表2、廢棄物活度監測器之最低可測活度(Bq/g) 密度 (g/cm3) 57Co 54Mn ,37Cs 60C〇 0.15 0. 059 0.018 0.019 0.0095 0.5 0. 021 0.0058 0.0061 0.0029 0.75 0. 018 0.004 0.0042 0. 002 1.13 0. 013 0. 003 0.0032 0.0014 1.8 0.0084 0. 0017 0.0018 0.00075 2.5 0.0088 0. 0018 0.0018 0.00083 3.0 0. 015 0. 0019 0. 002 0.0008 (4-2)計算公式 總計數 Μ 二 A,· p,K ! +RX EX/) 其中 為:137Cs核種活度(Bq) f / : 137Cs能量662 keV之光子偵測效率(%) A : 137Cs能量662 keV之光子分支比(%) A :各核種相對於137Cs之活度比 五X :各核種相對於137Cs之偵測效率比 ⑻核種活度比=/為 為C:某核種活度(HPGe分析結果) (b)核種偵測效率比尽= /f/A. 廢棄物偵測某加馬能量光子效率(%) :某核種發射光子分支比(%) 1317023 .· (C)器示加馬總活度為=从/私 * 137Cs偵測效率五/ =心尸 (^)指標核種活度冷=為/1〈/+尺^:五^’任意核種活度 ^x=A,· X Rx ⑻外釋導出限值Σ次/人,^7 4,〆某k種之活度限值(導出限值) (4-3)多核種分析 在校正假體内放置七片均勻面射源n7cs (72〗05Bq)、 鲁 54Mn ( 45309Bq)、6°Co (86048Bq )及 57C〇 (42777Β(〇,其標準 總活度為246239Bq,核種活度比率57Co: 54Mn:6QC0: 137Cs 為 0.593 : 0.628 : 1.19 : :1。使用 l37Cs 效率計算密度〗.lgcm_3、 1 ·8 gem 3 及 2.5 gcm_3 樣品之總活度結果如表3’而經由上述計 算公式之修正樣品的四種核種活度後,與標準點射源總活度 比較準確度之差異分別為1.82 %、2.59 %及1.74 %。 (私3-1)密度l lgcm-3假馥之137Cs效率計測 指標核種活度Ai為l37cs時之總活度At== 321197 Bq ’ 57C〇、54Mn 及 6°C〇 相對 137Cs 的尽為 0.23、1. 01 及 1· 30 :The maximum measurable activities of Mn, 6°Co and I37CS are 〇. 〇〇9Bq /g, 0.001 Bq /g and 〇. 〇1〇Bq /g, 54Mn and mCs are closer to their various enthalpies. The materials such as cloth, water, iron pipe and steel bar are very similar. In addition, the minimum measurable activity (Bq/g) of Mn, Co and 137Cs can meet the ex-factory release limit of the competent authority, and the minimum measurable activity of the measuring instrument should be lower than the IAEA of the International Atomic Energy Agency. The requirements for the nuclear export derivation limits of the specification (eg, 54 Mn, % 〇, and 137 Cs are 0. lBq/g). In addition, refer to the operation manual of the cleaning waste monitor of Antech Company type 3300-200. The minimum measurable activities of the instruments measuring 6QCo and 137Cs in the background of 2 minutes are 〇. 〇〇9 Bq /g and 0. 015 Bq/g' is similar to the lowest measurable activity of the instrument of this study activity monitor. In addition, 'observing the relationship between the minimum measurable activity (MDA) and the day ττ of the plastic flash detector, 'when the s ten time is lmin, 2 min, 5 min, 8 min and 10 min, The change of the lowest measurable activity of the 6CCo and the 137Cs is reduced by 1.9 times and the minimum measurable activity of the 137Cs is reduced by 1 min when the measurement time is extended from 5 min to 5 min. 2. 0 times; the minimum measurable activity of 6GCo and 137Cs is reduced by 2.5 times and 2.7 times when the measurement time is extended from 1 min to 1 〇min, respectively, when it is extended from 8 111 丨 11 to 1 〇 111 丨 11 The lowest measurable activity of 6()(^〇 and 137匚5 1317023) also changed little, only 9% and 15% respectively. Table 2. Minimum measurable activity of waste activity monitor (Bq/g Density (g/cm3) 57Co 54Mn, 37Cs 60C〇0.15 0. 059 0.018 0.019 0.0095 0.5 0. 021 0.0058 0.0061 0.0029 0.75 0. 018 0.004 0.0042 0. 002 1.13 0. 013 0. 003 0.0032 0.0014 1.8 0.0084 0. 0017 0.0018 0.00075 2.5 0.0088 0. 0018 0.0018 0.00083 3.0 0. 015 0. 0019 0. 002 0.0008 (4-2) Calculate the total formula Μ 2 A, · p, K ! +RX EX/) For: 137Cs nuclear activity (Bq) f / : 137Cs energy 662 keV photon detection efficiency (%) A : 137Cs energy 662 keV photon branch ratio (%) A: activity of each nucleus relative to 137Cs than five X : Detection efficiency ratio of each nucleus to 137Cs (8) Nuclear activity ratio = / is C: a nuclear activity (HPGe analysis result) (b) Nuclear detection efficiency ratio = / f / A. Waste detection A certain horse energy photon efficiency (%): a nuclear emission photon branch ratio (%) 1317023 . · (C) shows the total activity of the horse is = from / private * 137Cs detection efficiency five / = heart corpse (^) Index nuclear activity cold = is /1 < / + rule ^: five ^ 'any nuclear activity ^ x = A, · X Rx (8) external release derived limit Σ times / person, ^ 7 4, 〆 a k species Activity limit (export limit) (4-3) Multi-nuclear analysis placed seven uniform surface sources n7cs (72〗 05Bq), Lu 54Mn (45309Bq), 6°Co (86048Bq) and 57C in the calibration prosthesis 〇 (42777Β (〇, its standard total activity is 246239Bq, nuclear activity ratio 57Co: 54Mn: 6QC0: 137Cs is 0.593: 0.628: 1.19 : :1). Calculate the density using l37Cs efficiency. The total activity of the samples of lgcm_3, 1 ·8 gem 3 and 2.5 gcm_3 is shown in Table 3' and the total activity of the standard point source is corrected after the four nucleus activities of the sample are corrected by the above formula. The differences in accuracy were 1.82%, 2.59%, and 1.74%, respectively. (Private 3-1) Density l lgcm-3 false 馥 137Cs efficiency measurement index nuclear activity Ai is l37cs total activity At== 321197 Bq '57C〇, 54Mn and 6°C〇 relative to 137Cs is 0.23 , 1. 01 and 1· 30 :
Ai = At / Σ(^+ RxE^ ) -321197 / [ 1+(0.593x0.23)+(0.628xl.01)+(1.19x ' 1.30)] - 73500 Bq * Ax = Ai x ^x, 57Co=Ai x 0.593 = 43586 Bq 54Mn=Ai x 0.628-46158 Bq 6〇c〇=Ai x 1.19 = 87465 Bq 修正後之加馬總活度At = 250709 Bq i6 .1317023 標準點射源加馬總活度=246239 Bq 修正總活度與標準總活度之差異=3.36% (4-3-2)密度1. 8gcnf3假體之137Cs效率計測 指標核種活度Ai為mCs時之總活度At = 327780 Bq, 、54Mn 及 60C〇 相對 137Cs 的&為 0.17、0. 79 及 1. 11 :Ai = At / Σ(^+ RxE^ ) -321197 / [ 1+(0.593x0.23)+(0.628xl.01)+(1.19x ' 1.30)] - 73500 Bq * Ax = Ai x ^x, 57Co =Ai x 0.593 = 43586 Bq 54Mn=Ai x 0.628-46158 Bq 6〇c〇=Ai x 1.19 = 87465 Bq Corrected total activity of the gamma At = 250709 Bq i6 .1317023 Standard point source plus horse total activity = 246239 Bq corrected total activity and standard total activity difference = 3.36% (4-3-2) density 1. 8gcnf3 prosthesis 137Cs efficiency measurement index nuclear activity Ai is mCs total activity At = 327780 Bq, , 54Mn and 60C 〇 relative to 137Cs & 0.17, 0.79 and 1. 11 :
Ai=At/Z(l+^^) =327780 / [ 1+(0.593χ0.17)+(0.628x0.79)+( 1.19X 1.11)] = 74058 Bq Ax = Ai x Rx » 57Co = Ai x 0.593 = 43916 Bq 54Mn=Ai x 0.628 = 46508 Bq 60C〇-Ai x 1.19- 88129 Bq 修正後之加馬總活度At = 252611 Bq 標準點射源加馬總活度=246239 Bq 修正總活度與標準總活度之差異=2.59% 密度2. 5 gcm-3假體之u7Cs效率計測 指標核種活度Ai為137Cs時之總活度At = 325651 Bq, ' Co、54Mn 及 60c〇 相對 137Cs 的&為 0.16、0. 77 及 0. 99 :Ai=At/Z(l+^^) =327780 / [ 1+(0.593χ0.17)+(0.628x0.79)+( 1.19X 1.11)] = 74058 Bq Ax = Ai x Rx » 57Co = Ai x 0.593 = 43916 Bq 54Mn=Ai x 0.628 = 46508 Bq 60C〇-Ai x 1.19- 88129 Bq Modified total activity of the gamma At = 252611 Bq Standard point source plus total activity = 246239 Bq Total activity and standard total Activity difference = 2.59% Density 2. 5 gcm-3 prosthesis u7Cs efficiency measurement index Nuclear activity Ai is 137Cs total activity At = 325651 Bq, 'Co, 54Mn and 60c 〇 relative 137Cs & 0.16, 0. 77 and 0. 99:
Ai=At/X(l+^£x) = 325651 / [ 1+(0.593χ0.16)+(0.628χ0.77)+(1.19χ 0.99)〕二 185345 BqAi=At/X(l+^£x) = 325651 / [ 1+(0.593χ0.16)+(0.628χ0.77)+(1.19χ 0.99)]二 185345 Bq
Ax=Ai X 兄,57Co = Ai x 0.593 = 43552 Bq 54Mn=Ai x 0.628 = 46123 Bq 1317023 60Co=Ai x 1.19 = 87398 Bq 修正後之加馬總活度At = 250517 Bq 標準點射源加馬總活度=246239 Bq 修正總活度與標準總活度之差異=1.74 % 參數 gem'3 57Co 54Mn ^Co Rx 0.593 0.628 1.19 Px 96% 100% 200% ί'.ν 1.1 3.5 % 14.5% 16.6% 1.8 2.5 % 11.4% 14.1 % 2.5 2.4 % Π.1 % 12.7% 137Ax=Ai X brother, 57Co = Ai x 0.593 = 43552 Bq 54Mn=Ai x 0.628 = 46123 Bq 1317023 60Co=Ai x 1.19 = 87398 Bq Corrected total activity of the gamma At = 250517 Bq Standard point source Jiama total live Degree = 246239 Bq Corrected difference between total activity and standard total activity = 1.74 % Parameter gem'3 57Co 54Mn ^Co Rx 0.593 0.628 1.19 Px 96% 100% 200% ί'.ν 1.1 3.5 % 14.5% 16.6% 1.8 2.5 % 11.4% 14.1 % 2.5 2.4 % Π.1 % 12.7% 137
Cs 1 85% 綜合上述本發明提供之體校 下列優點⑴本系統之t、、二體,㈣决 (Bq/g) ’均可符合主管機關之 c°的取低可剛 倍的要求,適合計職贿均勻_ =準_導出限 估結果,如樣品為非單—核種茛棄物。(2)系統之性 對應關係值、能量依持因^枋,需依照核種密度與欵 加馬活度計算方法修正,驗妙=度比轉參數,進Cs 1 85% The following advantages are provided by the above-mentioned body provided by the present invention (1) The t, the two bodies, and the (four) decision (Bq/g) of the system can meet the requirements of the lower limit of the c° of the competent authority, and are suitable for Calculate the bribes evenly _ = quasi _ export limited evaluation results, such as samples are non-single-nuclear discards. (2) The nature of the system Correspondence value, energy dependence, 需, according to the nuclear density and 欵 马 活 计算 计算 计算 , , , 验 验 验 验 验 验
於5%。⑶四個核種的單-均、;:=射源活度的差 正假體的活度均勻性<7.9 %。 貝組成之多密度體射 飯體的密度與能量範圍廣,其建立的多岔度體射源」 之外釋物質的準確度。 則政率提南量測核設施丨 1317023At 5%. (3) Single-average of four nuclear species;: = difference of activity of the positive activity The uniformity of activity of the positive prosthesis <7.9%. The multi-density body of the shell consists of a wide range of densities and energies, and the built-in multi-twisted body source is the accuracy of the released material. Then the political rate of the South to measure the nuclear facilities 丨 1317023
唯以上所述者,僅為本發明之較佳實施例,當不能以之 限制本發明範圍。即大凡依本發明申請專利範圍所做之均等 變化及修飾,仍將不失本發明之要義所在,故都應視為本發 明的進一步實施狀況。 19 1317023 【圖式簡單說明】 圖一係為廢棄物活度監測器與體射源校正假體示意圖。 圖二A係為制式容器立體示意圖。 圖二B係為板體與射源板體堆疊示意圖。 圖三A係為本發明之射源板體較佳實施例剖面示意圖。 圖三B係為本發明之射源板體之射源分佈示意圖。 圖四係為本發明量測與校正方法較佳實施例示意圖。 圖五係為不同密度核種之儀器最低可測活度。 圖六係為監測器之儀器最低可測活度與計測時間關係。 圖七係為不同密度校正假體之各種能量光子效率。 【主要元件符號說明】 1- 廢棄物活度監測器 10- 屏蔽體 100-檢測空間 11- 輻射活度偵檢器 12- 微電腦處理器 2- 體射源校正假體 20- 制式容器 21- 内部空間 22- 板體 23- 射源板體 230-上護貝層 20 1317023 231-射源層 2310-射源 2 3 2 _防漏;慮紙層 233-下護貝層 3-校正方法 30〜34-流程The above is only the preferred embodiment of the present invention, and the scope of the present invention is not limited thereto. That is, the equivalent changes and modifications made by the invention in accordance with the scope of the present invention will remain without departing from the scope of the present invention and should be considered as further implementation of the present invention. 19 1317023 [Simple description of the diagram] Figure 1 is a schematic diagram of the dental activity monitor and the body source calibration prosthesis. Figure 2A is a perspective view of a standard container. Figure 2B is a schematic diagram of stacking of the plate body and the source plate body. Figure 3A is a cross-sectional view showing a preferred embodiment of the source plate of the present invention. FIG. 3B is a schematic diagram showing the source distribution of the source plate body of the present invention. Figure 4 is a schematic diagram of a preferred embodiment of the measurement and correction method of the present invention. Figure 5 shows the minimum measurable activity of instruments of different density nuclear species. Figure 6 shows the relationship between the minimum measurable activity of the instrument and the measurement time. Figure 7 shows the various energy photon efficiencies of different density corrected prostheses. [Main component symbol description] 1- Waste activity monitor 10 - Shield 100 - Detection space 11 - Radiation activity detector 12 - Microcomputer processor 2 - Body source calibration prosthesis 20 - System container 21 - Internal Space 22 - Plate 23 - Source plate 230 - Upper shell layer 20 1317023 231 - Source layer 2310 - Source 2 3 2 _ Leak proof; Paper layer 233 - Lower shell layer 3 - Correction method 30~ 34-flow
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| TWI606251B (en) * | 2016-08-02 | 2017-11-21 | 行政院原子能委員會核能研究所 | Mesurement system, calibration and mesurement method for bulk radiation wastes |
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| TWI661212B (en) * | 2018-07-09 | 2019-06-01 | 行政院原子能委員會核能研究所 | Calibration and measurement method and system for piping radioactivity contamination |
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