• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.4 no.4
• /
• pp.311-320
• /
• 2006

Removal characteristics of $H^{14}CO_3$ ion from IRN-150 mixed resin contaminated with $^{14}C$ radionuclide and a gasification behavior of $^{14}C$ radionuclide to $^{14}CO_2$ were investigated. The stripping solutions used for the removal of $^{14}C$ from spent resin were $NaNO_3,\;Na_3PO_4,\;NH_4H_2PO_4,\;H_3PO_4$. The influence of stripping solution concentration on the desorption characteristics of inactive $HCO_3$ ion into stripping solution from IRN-150 mixed resin and the gasification of this ion to $CO_2$ was analyzed. The gasification behavior to $CO_2$ by using NaOH, $HNO_3$, HCl was also compared to that of phosphate solution. Real spent resin stored in Wolsung nuclear power plant was used to evaluate the gasification characteristics of $^{14}C$ radionuclide to $^{14}CO_2$. Gamma radionuclides such as $^{137}Cs,\;^{60}Co$ in residual striping solutions after desorption experiment were analyzed.

• Nuclear Engineering and Technology
• /
• v.29 no.6
• /
• pp.17-28
• /
• 1997

콘크리트를 통한 핵종의 확산계수는 처분장으로 부터의 핵종 유출을 평가하는데 중요한입력 인자이다. 본 연구에서는 콘크리트에서의 핵종확산 연구 현황 및 핵종화산에 미치는 주요 인자들의 영향 등이 조사되었고, 주요 핵종의 확산계수가 직접 측정되었다. 내부확산법으로 측정된 확산계수값은 시료의 물과 시멘트 비 (W/C)가 증가할수록 증가하였으나 거의 같은 승수내에 있었으며, 공극확산이 핵종이동을 지배하였다. Cs 과 I 의 겉보기 확산계수는 순수 시멘트에서 각각 $1.0{\times}10^{-12}~1.0{\times}10^{-11}m^2/s$ 및 $3.0{\times}10^{-14}~1.0{\times}10^{-13}m^2/s$, 몰타르에서는 각각 $3.0{\times}10^{-12}~9.0{\times}10^{-11}m^2/s$ 및 $3.0{\times}10^{-11}m^2/s$의 범위에 있었다. 이와 병행하여 시멘트, 몰타르 및 콘크리트에서의 주요 방사성핵종의 확산계수 값을 문헌으로부터 수집, 정리하였다. 대상 핵종은 Cs, I, Sr, C, Co, H, Am, PU, Ni, Mn, Fe, Nb 및 Tc로서 수집된 핵종확산계수 값은 시료의 조건 (공극률 밀도, W/C 비, 온도 등) 에 따라 큰 편차를 보여주고 있다.

• Journal of Radiation Protection and Research
• /
• v.35 no.1
• /
• pp.12-20
• /
• 2010

In a primary system at nuclear power plants (NPPs), various radionuclides including fission products and corrosion products are generated due to the complex water conditions. Particularly, $^3H,\;^{14}C,\;^{58}Co,\;^{60}Co,\;^{137}Cs,\;and^{131}I$ are important radionuclides in respect of dose assessment for radiation workers and management of radioactive effluents. In this paper, the dominant contributors of radiation exposure for radiation workers and the member of public adjacent to NPPs were reviewed and the process of dose assessment attributable to those contributors were introduced. Furthermore, the analysis for some examples of radiation exposure to radiation workers and the public during the NPP operation was carried out. This analysis included the notable precedents of internal radiation exposure and contamination of demineralized water occurred in Korean NPPs. Particularly, the potential issue about the dose assessment of tritium and carbon-14 was also reviewed in this paper.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1995.05b
• /
• pp.839-844
• /
• 1995

처분장 구조물의 주요방벽 재료중의 하나인 콘크리트에서의 핵종확산계수를 측정하기 위하여 내부확산법을 적용하였다. 핵종은 양이온과 음이온을 대표하는 Cs 과 I 이었으며, 고체 시료는 양생된 순수시멘트 또는 시멘트와 모레를 섞은 몰타르로 물과 시멘트의 비 (W/C) 를 변화시켰다. 용액은 표준 제조방법에 따라 제조된 합성지하수이었다. Curve fitting 법을 이용한 모델과 실험의 비교로부터 핵종의 확산계수를 계산하였다. 순수시멘트의 경우 Cs 의 겉보기 확산계수는 1.7 $\times$ $10^{-12}$~1.4 $\times$ $10^{-11}$ m$^2$/sec 의 범위로 W/C 가 증가할수록 컸으며 I 는 2.9 $\times$ $10^{-14}$ ~ 1.0 $\times$ $10^{-l3}$ $m^2$/sec의 범위로 또한 W/C 에 따라 증가하였다. 몰타르의 경우 W/C 가 클수록 Cs 의 확산계수는 증가하였으나 I 에 대해서는 큰 변화를 보여주지 않았다 본 실험에서 얻어진 핵종의 유효확산계수값이 $10^{-13}$ ~ $10^{-10}$ m$^2$/sec의 범위를 갖는 것으로 보아 공극확산이 핵종확산의 지배 메커니즘임이 예상되었다.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2004.06a
• /
• pp.52-57
• /
• 2004

In order to analyze key parameters of important radionuclides in dose evaluation model of decommissioning site, a sensitivity analysis was performed. This analysis assumed a resident farmer for an exposure scenario and 0.037Bq/g for the concentration of radionuclides. As a result of sensitivity analysis, the key parameters of radionuclides considered were the area of contaminated zone, external gamma shielding factor and indoor time fraction for Cs-137 and Co-60. The key parameters for C-14 were the environmental parameters and hydrological parameters of unsaturated zone. Also, the key parameter for Sr-90 was the density of contaminated zone.

• Journal of Radiation Protection and Research
• /
• v.26 no.4
• /
• pp.375-384
• /
• 2001

It is possible to count and perform quench correction on two ${\beta}$ -label samples so long as the maximum ${\beta}$-energies are sufficiently different. However, when 4he conventional technique is applied to the radioassay of a mixture of more than three nuclides, the reliability of the activities determined is considerably reduced, resulting from the large overlapping of liquid scintillation pulse height distributions of each nuclide. A technique that allows the activities of multiple ${\beta}$-labeled samples to be radioassayed was proposed by using the least square method. The technique was applied to mixture samples of $^3H,\;^{14}C,\;^{36}Cl$, and $^{90}Sr$. The analytical values were in good agreement with the reference values within 7% relative error.

• Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
• /
• v.4 no.4
• /
• pp.373-384
• /
• 2006

Spent ion-exchanged resin generated from various purification systems in CANDU reactor was contaminated with high activity of $^{14}C$ radionuclide. This paper describes the results of fundamental study to develop the applicable technology for the treatment of this spent resin. Based on the adsorption capacity of inactive $HCO_3$ ion and other anions on IRN-150 mixed resin, the removal characteristics of $HCO_3$ ion adsorbed on to IRN-150 by various stripping solutions were evaluated. Maximum adsorption amount of the $HCO_3$ ion onto IRN-150 raw resin was about 11 mg-C/g-resin which agrees with the theoretical adsorption amount of this resin. Adsorption affinity of various anions such as $CS,\;CO,\;Na\;NH_4$ was analyzed in single and multi-component systems. From the results of removal characteristics of the $HCO_3$ ion adsorbed on IRN-150 by various stripping solutions, $NH_4H_2PO_4$ stripping solution is more effective than $NaNO_3,\;Na_3PO_3$ solutions for the complete removal of $^{14}C$ radionuclide from the IRN-150 spent resin.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2004.06a
• /
• pp.147-157
• /
• 2004

The production of $^{14}C$ occurs in the Moderator(MOD), Primary Heat Transport System (PHTS), Annulus Gas System(AGS) and Fuel in the CANDU reactor. Among the four systems, The MOD system is the largest contributor to $^{14}C$ production(approximately 94.8%). $^{14}C$ is distributed of $^{14}CO_2$, $H_2^{14}CO_3$, $H^{14}{CO_3}^-$ and $^{14}{CO_3}^{2-}$ species as a function of the pH of water. Of these species, $H_2^{14}CO_3$ and $H^{14}{CO_3}^-$ form are predominant because the pH of MOD system is ＞ 5. In this paper, adsorption-desorption characteristics of bicarbonate ion (${HCO_3}^-$) by IRN 150 resin was investigated. ${HCO_3}^-$ ion existed in neutral condition(app. pH 7)was reacted with ion exchange resin (IRN-150) and saturated with it. Then $NaNO_3$ and $Na_3PO_4$ solutions selected as extraction materials were used to make an investigation into feasibility of ${HCO_3}^-$ extraction from resin saturated with ${HCO_3}^-$. Desorption of $CO^{2+}$ and $Cs^+$ ion by $Na^+$ ion was not occurred, and desorption of ${HCO_3}^-$ ion by ${NO_3}^-$ and ${PO_4}^{3-}$ was occurred slowly. Also, the status of ion exchange which is used in Wolsong NPPs and generation of spent resin yearly were surveyed.

• Proceedings of the Korean Radioactive Waste Society Conference
• /
• 2005.06a
• /
• pp.284-289
• /
• 2005

According to the nuclear safety regulation policy including the administration of radionuclides in low level radwastes, the evaporator bottoms were mixed with cement to form a stable solidification for identifying the recovery possibility of the C-14. The chemical oxidation method was applied for the extraction of C-14 from the cement waste form. The emitting beta ray of the C-14 extracted from the radwastes was measured with the liquid scintillation counter and calculated by using the quenching correction curves. Only the beta emitting radioactive nuclides of the C-14 in the radwastes was showed the radioactivities with the range of $2.7E+00\;{\sim}\;3.07E+02$ Bq/g.

• Proceedings of the Korean Nuclear Society Conference
• /
• 1998.05a
• /
• pp.157-162
• /
• 1998

양전자 단층 촬영장치(PET)에 사용되는 주요 양전자 방출 핵종들의 생성 단면적을 평가하였다. 평가한 생성 반응들은 $^{14}$ N(p,$\alpha$)$^{11}$ C,$^{16}$ O(p,$\alpha$)$^{13}$N, $^{14}$ N(d,n)$^{15}$ O,$^{18}$ O(p,n)$^{18}$ F,$^{20}$ Ne(d,$\alpha$)$_{18}$ F 이며, 입사 입자의 에너지 범위는 반응 문턱 에너지부터 약 150 MeV까지이다. 또한 하전입자 범 모니터용 표준 단면적으로서 $^{27}$ Al에 d 및 $^3$He, $\alpha$가 반응하여 $^{22}$ Na가 생성되는 반응의 단면적들을 입사 에너지 약 120 MeV까지 평가하였다. 실험치를 fitting하게나 ALICE95 코드를 이용하여 이론적 계산을 수행하였는데, 평가 단면적의 표준 편차는 10-30%이다 이들 평가 단면적들은 가속기를 이용한 PET용 핵종의 생산율 계산 및 빔 모니터의 표준 단면적으로 사용하기에 적절한 것으로 판단된다.