• 한국해양환경ㆍ에너지학회지
• /
• 제19권1호
• /
• pp.18-24
• /
• 2016

광물탄산화는 이산화탄소를 칼슘, 마그네슘 등을 함유한 금속산화물과 반응시켜 영구적으로 저장하는 기술이다. 본 연구에서는 직접탄산화 방법으로 이산화탄소를 저장하기 위해 해수와 알칼리성 산업부산물인 제지슬러지소각재(PSA)를 사용하였다. 다양한 실험을 통해 해수와 PSA를 이용한 직접탄산화 반응의 최적 용매의 양(해수와 PSA의 혼합비)과 반응시간을 찾았고, PSA를 이용한 직접탄산화 반응에 해수와 초순수를 각각 용매로 사용했을 때의 이산화탄소 저장량을 비교하였다. 이산화탄소 저장량은 탄산화반응 후 고체증가량과 열중량분석 결과를 이용해서 계산하였다. 실험에 사용한 PSA는 미세하고 67.2%의 칼슘을 포함하였다. $25^{\circ}C$, 1기압에서 해수를 PSA와 혼합하여 이산화탄소를 0.05 L/min 유량으로 주입하는 탄산화반응의 최적 용매의 양과 반응시간은 각각 5 mL/g, 2시간이었다. 해수와 초순수를 용매로 사용해서 PSA와 각각 혼합한 다음 탄산화했을 때, 이산화탄소 저장량은 각각 113, $101kg\;CO^2/(ton\;PSA)$이었다. 해수를 사용하여 탄산화한 고체는 대부분 calcite 형태의 탄산칼슘과 소량의 탄산마그네슘으로 구성되어있었고, 초순수를 사용했을 때의 고체도 calcite 형태의 탄산염임을 확인하였다.

• Nuclear Engineering and Technology
• /
• 제50권8호
• /
• pp.1234-1245
• /
• 2018

The risk of multi-unit nuclear power plants (NPPs) at a site has received considerable critical attention recently. However, current probabilistic safety assessment (PSA) procedures and computer code do not support multi-unit PSA because the traditional PSA structure is mostly used for the quantification of single-unit NPP risk. In this study, the main purpose is to develop a multi-unit Level 2 PSA method and apply it to full-power operating six-unit OPR1000. Multi-unit Level 2 PSA method consists of three steps: (1) development of single-unit Level 2 PSA; (2) extracting the mapping data from plant damage state to source term category; and (3) combining multi-unit Level 1 PSA results and mapping fractions. By applying developed multi-unit Level 2 PSA method into six-unit OPR1000, site containment failure probabilities in case of loss of ultimate heat sink, loss of off-site power, tsunami, and seismic event were quantified.

• Asian Pacific Journal of Cancer Prevention
• /
• 제17권6호
• /
• pp.2941-2946
• /
• 2016

Background: The limitations of total serum PSA values remain problematic, especially after an initial negative prostate biopsy. In this prospective study of Chilean men with a continued suspicion of prostate cancer due to a persistently elevated total serum PSA, abnormal digital rectal examination and initial negative prostate biopsy were compared with the use of the on-line Chun nomagram, detection of primary malignant circulating prostate cells (CPCs) and free percent PSA to predict a positive second prostate biopsy. We hypothesized that men negative for circulating prostate cells have a small risk of clinically significant prostate cancer and thus may be conservatively observed. Men positive for circulating prostate cells should undergo biopsy to confirm prostate cancer. Materials and Methods: Consecutive men with a continued suspicion of prostate cancer underwent 12 core TRUS prostate biopsy; age, total serum PSA and percentage free PSA and Chun nomagram scores were registered. Immediately before biopsy an 8ml blood simple was taken to detect primary mCPCs. Mononuclear cells were obtained by differential gel centrifugation and identified using double immunostaining with anti-PSA and anti-P504S. Biopsies were classifed as cancer/no-cancer, mCPC detecton test as negative/positive and the total number of cells/8ml registered. Areas under the curve (AUC) for percentage free PSA, Chun score and CPCs were calculated and compared. Diagnostic yields were calculated with reference to the number of possible biopsies that could be avoided and the number of clinically significant cancers that would be missed. Results: A total of 164 men underwent a second biopsy; 41 (25%) had cancer; the AUCs were 0.65 for free PSA, 0.76 for the Chun score and 0.87 for CPC detection, the last having a significantly superior prediction value (p=0.01). Using cut off values of free PSA <10%, Chun score >50% and ${\geq}1$ CPC detected, CPC detection had a higher diagnostic yield. Some 4/41 cancers complied with the criteria for active surveillance, free PSA and the Chun score missed a higher number of significant cancers when compared with CPC detection. Conclusions: Primary CPC detection outperformed the use of free PSA and the Chun nomagram in predicting clinically significant prostate cancer at repeat prostate biopsy.

• 폴리머
• /
• 제35권4호
• /
• pp.363-369
• /
• 2011

콘크리트 제조 시 사용되는 잉여수를 지연 흡수시키기 위하여 역유화중합법으로 중합된 가교 poly(sodium acrvlate) (cPSA)를 ethylene glycol dimethacrylate(EGDMA)로 표면 가교시켰다. cPSA의 제조에서 연속상은 paraffin liquid, 단량제는 8 M 농도의 NaOH 수용액으로 90% 중화된 acrylic acid(AA), 가교제는 N,N-methylene bisacrylamide(MBA), redox 개시제는 ammonium persulfate(APS)와 sodium metabisulfite(SMBS)를 사용하여 역유화중합법으로 제조하였다. 제조된 cPSA는 EGDMA플 사용하여 표면 가교 반응을 수행하였다. 시멘트 수용액에서 $Ca^{2+}$ 이온과 cPSA의 상호 작용을 관찰하기 위하여 FTIR spectroscopy 분석법을 사용하였다. 제조된 흡수제들을 탈이온수 $Ca(OH)_2$ 수용액(pH 12) 및 시멘트 포화 수용액에서의 팽윤비를 측정하였으며, cPSA는 2시간만에 팽윤이 완료되었지만, 표면이 가교된 cPSA-EGDMA는 3시간 후 팽윤이 거의 완료되는 것을 관찰하였다. 또한 합성한 cPSA-EGDMA를 첨가함으로써 시멘트의 응결시간과 모르타르의 압축강도 증가를 관찰하였다.

• Nuclear Engineering and Technology
• /
• 제43권3호
• /
• pp.271-278
• /
• 2011

When performing fire PSA in a nuclear power plant, an event mapping method, using an internal event PSA model, is widely used to reduce the resources used by fire PSA model development. Feasible initiating events and component failure events due to fire are identified to transform the fault tree (FT) for an internal event PSA into one for a fire PSA using the event mapping method. A surrogate event or damage term method is used to condition the FT of the internal PSA. The surrogate event or the damage term plays the role of flagging whether the system/component in a fire compartment is damaged or not, depending on the fire being initiated from a specified compartment. These methods usually require explicit states of all compartments to be modeled in a fire area. Fire event scenarios, when using explicit identification, such as surrogate or damage terms, have two problems: (1) there is no consideration of multiple fire propagation beyond a single propagation to an adjacent compartment, and (2) there is no consideration of simultaneous fire propagations in which an initiating fire event is propagated to multiple paths simultaneously. The present paper suggests a fire propagation equation to identify all possible fire event scenarios for an explicitly treated fire event scenario in the fire PSA. Also, a method for separating fire events was developed to make all fire events a set of mutually exclusive events, which can facilitate arithmetic summation in fire risk quantification. A simple example is given to confirm the applicability of the present method for a $2{\times}3$ rectangular fire area. Also, a feasible asymptotic approach is discussed to reduce the computational burden for fire risk quantification.

• 한국안전학회지
• /
• 제27권5호
• /
• pp.229-234
• /
• 2012

Operator's action time is evaluated from MAAP4 analysis used in conventional probabilistic safety assessment(PSA) of a nuclear power plant. MAAP4 code which was developed for severe accident analysis is too conservative to perform a realistic PSA. A best-estimate code such as RELAP5/MOD3, MARS has been used to reduce the conservatism of thermal hydraulic analysis. In this study, operator's action time of core cooling recovery operation is evaluated by using the MARS code, which its Fussell-Vessely(F-V) value was evaluated as highly important in a small break loss of coolant(SBLOCA) event and loss of component cooling water(LOCCW) event in previous PSA. The main conclusions were elicited : (1) MARS analysis provides larger time window for operator's action time than MAAP4 analysis and gives the more realistic time window in PSA (2) Sufficient operator's action time can reduce human error probability and core damage frequency in PSA.

• 한국안전학회지
• /
• 제34권3호
• /
• pp.102-110
• /
• 2019

This paper describes the work and results of the preliminary Probabilistic Safety Assessment (PSA) for a research reactor in the design phase. This preliminary PSA was undertaken to assess the level of safety for the design of a research reactor and to evaluate whether it is probabilistically safe to operate and reliable to use. The scope of the PSA described here is a Level 1 PSA which addresses the risks associated with core damage. After reviewing the documents and its conceptual design, eight typical initiating events are selected regarding internal events during the normal operation of the reactor. Simple fault tree models for the PSA are developed instead of the detailed model at this conceptual design stage. A total of 32 core damage accident sequences for an internal event analysis were identified and quantified using the AIMS-PSA. LOCA-I has a dominant contribution to the total CDF by a single initiating event. The CDF from the internal events of a research reactor is estimated to be 7.38E-07/year. The CDF for the representative initiating events is less than 1.0E-6/year even though conservative assumptions are used in reliability data. The conceptual design of the research reactor is designed to be sufficiently safe from the viewpoint of safety.

• 대한임상검사과학회지
• /
• 제41권2호
• /
• pp.76-82
• /
• 2009

It would be one of the most important tests that determination of semen in crime scene as a matter of significant evidences. Recently, it has been developed for the identification of semen in forensic specimens which was used simply, easily and reproductively. In this study, Prostate-Specific-Antigen (PSA) Rapid Test kit was evaluated for the forensic identification of semen and compared with one step semen inspection forensic rapid test kit. The sensitivity and specificity of the rapid PSA kit were examined in addition to the stability of PSA. The positive band of rapid PSA kit shown even with 1,000,000-fold diluted semen, which was at least 100 timed higher than qualitative one step semen inspection forensic rapid test kit. PSA was detected in urine from normal male adult, however, it was not detected in urine from young boys and female body fluids. It was shown that PSA was very stable to resist boiling for 20 minutes and the effect of bacteria. In crime scene investigation, rapid PSA kit is expected to help to identify semen easily in the evidences.

• Asian Pacific Journal of Cancer Prevention
• /
• 제16권2호
• /
• pp.601-606
• /
• 2015

Background: Prostate cancer is predominately a disease of older men, with a median age of diagnosis of 68 years and 71% of cancer deaths occurring in those over 75 years of age. While prostate cancer screening is not recommended for men >70 years, fit elderly men with controlled comorbidities may have a relatively long life expectancy. We compare the use of age related PSA with the detection of primary malignant circulating prostate cells mCPCs to detect clinically significant PC in this population. Materials and Methods: All men undergoing PC screening with a PSA >4.0ng/ml underwent TRUS 12 core prostate biopsy (PB). Age, PSA, PB results defined as cancer/no-cancer, Gleason, number of positive cores and percentage infiltration were registered. Men had an 8ml blood sample taken for mCPC detection; mononuclear cells were obtained using differential gel centrifugation and mCPCs were identified using immunocytochemistry with anti-PSA and anti-P504S. A mCPC was defined as a cell expressing PSA and P504S; a positive test as at least one mCPC detected/sample. Diagnostic yields for subgroups were calculated and the number of avoided PBs registered. Esptein criteria were used to define small grade tumours. Results: A total of 610 men underwent PB, 398 of whom were aged <70yrs. Men over 70 yrs had: a higher median PSA, 6.24ng/ml versus 5.59ng/ml (p=0.04); and a higher frequency of cancer detected 90/212 (43%) versus 134/398 (34%) (p=0.032). Some 34/134 cancers in men <70yrs versus 22/90 (24%) of men >70yrs complied with criteria for active surveillance. CPC detection: 154/398 (39%) men <70yrs were CPC (+), specificity for cancer 86%, sensitivity 88%, 14/16 with a false (-) result had a small low grade PC. In men >70 years, 88/212 (42%) were CPC (+); specificity 92%, sensitivity 87%, 10/12 with a false (-) had small low grade tumours. False (+) results were more common in younger men 36/154 versus 10/88 (p<0.02). With a PSA cutoff of 6.5ng/ml, in men <70yrs, 108 PB would be avoided, missing 56 cancers of which 48 were clinically significant. Using CPC detection, 124 biopsies would be avoided, missing only 2 clinically significant cancers. In men >70 yrs using a PSA >6.5ng/ml would have resulted in 108 PB with 34 PC detected, of which 14(41%) were small low grade tumours. Conclusions: The use of CPC detection in the fit elderly significantly decreases the number of PBs without missing clinically significant cancers, indicating superiority to the use of age-related PSA.

• 한국안전학회지
• /
• 제35권3호
• /
• pp.86-95
• /
• 2020

This paper describes the work and the results of the final Probabilistic Safety Assessment (PSA) for the Jordan Research and Training Reactor (JRTR). This final PSA was undertaken to assess the level of safety for the design of a research reactor and to evaluate whether it is probabilistically safe to operate and reliable to use. The scope of the PSA described here is a Level 1 PSA, which addresses the risks associated with core damage. After reviewing the documents and its conceptual design, nine typical initiating events were selected regarding internal events during the normal operation of the reactor. AIMS-PSA (Version 1.2c) was used for the accident quantification, and FTREX was used as the quantification engine. 1.0E-15/yr of the cutoff value was used to deliminate the non-effective Minimal Cut Sets (MCSs) when quantifying the JRTR PSA model. As a result, the final result indicates a point estimate of 2.02E-07/yr for the overall Core Damage Frequency (CDF) attributable to internal initiating events in the core damage state for the JRTR. A Loss of Primary Cooling System Flow (LOPCS) is the dominant contributor to the total CDF by a single initiating event (9.96E-08/yr), and provides 49.4% of the CDF. General Transients (GTRNs) are the second largest contributor, and provide 32.9% (6.65E-08/yr) of the CDF.