• Nuclear Engineering and Technology
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• 제51권7호
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• pp.1715-1720
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• 2019

Jozef Stefan Institute (JSI), TRIGA Mark II reactor employs the homogeneous mixture of uranium and zirconium hydride fuel type. Since its upgrade, a series of fresh fuel steady state experimental benchmarks have been conducted. The benchmark results have provided data for testing computational neutronics codes which are important for reactor design and safety analysis. In this work, we investigated the JSI TRIGA Mark II reactor neutronics characteristics: the effective multiplication factor and two safety parameters, namely the control rod worth and the fuel temperature reactivity coefficient using SuperMC. The modeling and real-time cross section generation methods of SuperMC were evaluated in the investigation. The calculation analysis indicated the following: the effective multiplication factor was influenced by the different cross section data libraries; the control rod worth evaluation was better with Monte Carlo codes; the experimental fuel temperature reactivity coefficient was smaller than calculated results due to change in water temperature. All the results were in good agreement with the experimental values. Hence, SuperMC could be used for the designing and benchmarking of other TRIGA Mark II reactors.

• Nuclear Engineering and Technology
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• 제18권2호
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• pp.78-84
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• 1986

일차섭동이론을 이용하여 물질밀도 감도 계수의 표현식을 유도하였다. Super-Phenix I 평형노심의 초기상태를 기준계로 택했으며 유효중배계수를 계의 응답함수로 정의했다. 볼츠만 연산자의 구성요 소인 물질밀도로 표현되는 핵연료의 농축도와 실효밀도를 입력변화로 선정했다. 위 계산을 수행하는데 전산코드시스템 (KAERI-26군 단면적 library/1DX/2DB/PERT-V)가 사용되었다. 핵연료 농축도의 유효증배계수에 대한 감도계수는 4.576로 계산되었으며, 핵연료 실효밀도의 감도 계수는 0.0756으로 계산되었다. 본 연구는 감도해석법이 대형전산코드를 이용한 직접반복계산법에 비해 계산시간의 단축과 아울러 많은 정보를 준다는 것을 보여준다.

• Nuclear Engineering and Technology
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• 제53권3호
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• pp.732-740
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• 2021

Scattering resonance of medium mass nuclides leads complex spectrum in the fast reactor, which requires thousands of energy groups in the spectrum calculation. When the broad-group cross sections are collapsed, reaction rate cannot be completely conserved. To eliminate the error from energy collapsing, the Super-homogenization method in energy collapsing (ESPH) was employed in the fast reactor code SARAX. An ESPH factor was derived based on the ESPH-corrected SN transport equation. By applying the factor in problems with reflective boundary condition, both the effective multiplication factor and reaction rate were conserved. The fixed-source iteration was used to ensure the stability of ESPH iteration. However, in the energy collapsing process of SARAX, the vacuum boundary condition was adopted, which was necessary for fast reactors with strong heterogeneity. To further reduce the error caused by leakage, an additional conservation factor was proposed to correct the neutron current in energy collapsing. To evaluate the performance of ESPH with conservation factor, numerical benchmarks of fast reactors were calculated. The results of broad-group calculation agreed well with the direct full-core Monte-Carlo calculation, including the effective multiplication factor, radial power distribution, total control rod worth and sodium void worth.

• Nuclear Engineering and Technology
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• 제14권3호
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• pp.138-147
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• 1982

열중성자로에 플루토늄의 재순환이 실현될 것에 대비하여 이의 해석을 위한 이론적인 기초를 수립하였다. 특히 상업적인 목적으로 플루토늄 재순환이 이루어질 때를 위하여 $UO_2$-PuO$_2$를 핵연료로 하는 균일격자 임계실험로에 대한 분석을 수행하였다. 이 목적을 위하여 GAM과 THERMOS에 이론적인 기초를 두고 $UO_2$-PuO$_2$계통의 해석에 적합한 이론을 가미하여 KARATE라는 이름의 단일세포격자코드를 개발하였다. KARATE에서 산출한 소수군 중성자 단면적과 확산이론 계산코드인 KIDD를 이용하여 임계실험로에 대한 유효증배계수를 계산하였다. 우리가 선정한 41개의 임계실험로에 대하여 유효증배계수의 평균치는 0.9997, 그 표준편차는 0.43%이었다. 이러한 결과는 KARATE/KIDD 전산체제가 $UO_2$-PuO$_2$를 핵연료로 하는 계통의 핵적 특성분석에 아주 유효하게 사용될 수 있다는 사실을 밝혀 준다.

• Journal of Radiation Protection and Research
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• 제8권1호
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• pp.33-37
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• 1983

물 또는 콘크리트반사체(反射體)의 두께 및 콘크리트반사체(反射體)와 핵물질용액계(核物質溶液系) 사이의 간격에 따라 변(變)하는 유효증배계수(有效增倍係數)로서의 반사효과(反射效果)를 중성자수송이론(中性子輸送理論)에 기초를 둔 각분할방법(角分割方法)의 전산코드 ANISN으로 계산하였다. 그 결과에 따르면 반사체(反射體)의 두께가 엷을 때, 유효증배계수(有效增倍係數)를 기준으로 한 물 반사체(反射體)의 반사효과(反射效果)는 콘크리트에서보다 크지만 그 두께가 커지면 반대현상도 생기는 것 같았다. 한편 핵물질용액계(核物質溶液系)와 콘크리트반사체(反射體)사이에 물이 채워져 있고 그 간격변화에 따라 산출한 유효증배계수치(有效增倍係數値)는 처음 급격하게 감소하다가 약 15cm를 지나면서부터 서서히 감소하는 것 같았다.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2002년도 춘계공동학술발표회요약집
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• pp.52-52
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• 2002

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2003년도 가을 학술논문집
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• pp.590-595
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• 2003

An Exponential experiment system which is composed of a neutron detector, a signal analysis system and a neutron source, Cf-252 has been installed in order to experimentally determine the neutron effective multiplication factor for a PWR spent fuel assembly. The axial background neutron flux is measured in a preliminary performance test. From the results, the spacer grid position is determined to be consistent with the design specifications within a 2.3% relative error. The induced fission neutron for four of the assemblies is also measured by scanning the neutron source, Cf-252 or the neutron detector. The exponential decay constants have been evaluated by the application of the Poisson regression to the net induced fission neutron counts. The measured keffs determined on the basis of the exponential decay constants of Cl5 appeared to be 0.541, 0.540, 0.597 and 0.556, respectively, which are comparable with 0.55195$\pm$0.00232 of the MCNP calculation.

• Journal of Radiation Protection and Research
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• 제7권1호
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• pp.56-60
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• 1982

핵분열(核分裂) 즉발중성자(卽發中性子)스펙트럼의 표현식(表現式)인 왓트식(式), 크란버그식(式) 및 멕스웰식(式)을 핵분열(核分裂)의 선원항(線源項)으로 취(取)하여 고디바계(系)와 제제벨계(系)의 유효증배계수(有效增倍係數)를 ANISN 전산(電算)코드로 산출(算出)하고 타(他) 연구자(硏究者)의 실험치(實驗値)와 비교(比較)해 보았다 .그 결과(結果) 실험치(實驗値)에 가장 가까운 값을 주는 것은 멕스웰식(式)으로 보였다. 이것은 곧 멕스웰식(式)이 핵분열(核分裂) 즉발중성자(卽發中性子)스펙트럼의 적절(適切)한 표현식(表現式)임을 의미(意味)한다.

• Nuclear Engineering and Technology
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• 제51권6호
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• pp.1708-1714
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• 2019

The purpose of the critical evaluation of the spent fuel pool (SFP) is to verify that the maximum effective multiplication factor ($K_{eff}$) is less than the critical safety limit at 100% stored condition of the spent fuel with the maximum reactivity. At nuclear power plants, the storage standard of spent fuel, ie, the loading curve, is established to prevent criticality from being generated in SFP. Here, the loading curve refers to a graph showing the minimum discharged burnup versus the initial enrichment of spent fuel. Recently, US NRC proposed the new critical safety assessment guideline (DSS-ISG-2010-01, Revision 0) of PWR SFPs and most of utilities in US is following it. Of course, the licensed criterion of the maximum effective multiplication factor of SFP remains unchanged and it should be less than 0.95 from the 95% probability and the 95% confidence level. However, the new guideline is including the new evaluation methodologies like the application of the axial burnup profile, the validation of depletion and criticality code, and trend analysis. Among the new evaluation methodologies, the most important factor that affects $K_{eff}$ is the axial burnup profile of spent fuel. US NRC recommends to consider the axial burnup profiles presented in NUREG-6801 in criticality analysis. In this paper, criticality effect was evaluated considering three profiles, respectively: i) Axial burnup profiles presented in NUREG-6801. ii) Representative PWR axial burnup profile. iii) Uniform axial burnup profile. As the result, the case applying the axial burnup profiles presented in NUREG-6801 showed the highest $K_{eff}$ among three cases. Therefore, we need to introduce a new methodology because it can be issued if the axial burnup profiles presented in NUREG/CR-6801 are applied to the domestic nuclear power plants without any other consideration.

• 전기의세계
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• 제14권2호
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• pp.36-38
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• 1965

원자제어제용 계측회로 및 제어장치를 이해하기 위해서는 원자로내의 중성자선속이 노의 반응도에 따라 시간적으로 어떻게 변하는가를 알 필요가 있다. 1개의 핵분열에서 평균 2.5개의 중성자가 방출하는데 그중 다음의 핵분열에 기여하는 중성자수를 Effective multiplication factor(실효증배계수) Keff라고 한다. 그런데 2.5개의 중성자가 모두 순간적으로 방출되는것은 아니며 약 0.7%의 분열 생성물은 약간 늦어서 방출한다. 이러한 누발 중성자는 분열생성물의 반감기에 따라 몇 개의 군으로 나누어 지지만 간단히 하기 위하여 한 개의 군으로 평균하여 생각하기로 한다.