• Nuclear Engineering and Technology
• /
• 제42권2호
• /
• pp.203-210
• /
• 2010

The $\underline{H}igh$ flux $\underline{A}dvanced$ $\underline{N}eutron$ $\underline{A}pplication$ $\underline{R}eact\underline{O}r$ (HANARO), an open-tank-in-pool type reactor, is one of the multi-purpose research reactors in the world. Since the commencement of HANARO's operations in 1995, a significant number of experimental facilities have been developed and installed at HANARO, and continued efforts to develop more facilities are in progress. Owing to the stable operation of the reactor and its frequent utilization, more experimental facilities are being continuously added to satisfy various fields of study and diverse applications. The irradiation testing equipment for nuclear fuels and materials at HANARO can be classified into capsules and the Fuel Test Loop (FTL). Capsules for irradiation tests of nuclear fuels in HANARO have been developed for use under the dry conditions of the coolant and materials at HANARO and are now successfully utilized to perform irradiation tests. The FTL can be used to conduct irradiation testing of a nuclear fuel under the operating conditions of commercial nuclear power plants. During irradiation tests conducted using these capsules in HANARO, instruments such as the thermocouple, Linear Variable Differential Transformer (LVDT), small heater, Fluence Monitor (F/M) and Self-Powered Neutron Detector (SPND) are used to measure various characteristics of the nuclear fuel and irradiated material. This paper describes not only the status of HANARO and the status and perspective of irradiation devices and instrumentation for carrying out nuclear fuel and material tests in HANARO but also some results from instrumentation during irradiation tests.

• Nuclear Engineering and Technology
• /
• 제52권4호
• /
• pp.661-673
• /
• 2020

The quarter-core simulation of BEAVRS Cycle 2 depletion benchmark has been conducted using the MCS/CTF coupling system. MCS/CTF is a cycle-wise Picard iteration based inner-coupling code system, which couples sub-channel T/H (thermal/hydraulic) code CTF as a T/H solver in Monte Carlo neutron transport code MCS. This coupling code system has been previously applied in the BEAVRS benchmark Cycle 1 full-core simulation. The Cycle 2 depletion has been performed with T/H feedback based on the spent fuel materials composition pre-generated by the Cycle 1 depletion simulation using refueling capability of MCS code. Meanwhile, the MCS internal one-dimension T/H solver (MCS/TH1D) has been also applied in the simulation as the reference. In this paper, an analysis of the detailed criticality boron concentration and the axially integrated assembly-wise detector signals will be presented and compared with measured data based on the real operating physical conditions. Moreover, the MCS/CTF simulated results for neutronics and T/H parameters will be also compared to MCS/TH1D to figure out their difference, which proves the practical application of MCS into the BEAVRS benchmark two-cycle depletion simulations.

• Journal of Radiation Protection and Research
• /
• 제22권3호
• /
• pp.219-226
• /
• 1997

환경시료 및 Swipe시료에서 방출되는 감마선을 측정 분석하기 위하여 극저준위 백그라운드 감마선 측정시스템을 설치하였다. 본 측정시스템은 백그라운드를 저감하기 위해 극저방사능 물질로 구성된 수동적 차폐방법, 우주선 영향을 차단하기 위한 역동시 측정법, 그리고 공기중 방사성 핵종인 라돈가스를 시스템 내부에서 제거하는 방법 등을 적용하고 있다. 적용된 백그라운드 저감법에 대한 성능시험 결과, 실험실 조건의 백그라운드 준위가 관심 대상 에너지 영역($50\;keV{\sim}2\;MeV$)에서 $10^{-2}$ order 정도로 저감되었다. 그리고 미신고 핵활동을 탐지하기 위한 관심 대상 핵종의 감마선 에너지 영역에서 평가된 시스템의 최소검출하한(MDA)값은 환경시료 분석에 적합한 것으로 평가되었다. 그러나 저에너지 영역에서는 여전히 우주선에 의한 중성자 영향이 백그라운드 요인으로 작용하고 있는 것으로 분석되었다.

• 전기의세계
• /
• 제14권1호
• /
• pp.5-12
• /
• 1965

In the designs of the sensitive electronic devices such as phase sensitive detector, X-ray diffractometer, and neutron diffractometers, we must take into account the geometrical factors in a coil systems and extraneous stray fields. Input wave forms in such a sensitive electronic devices are often altered by the influence of these factors. Since the magnitude of the stray fields is generally very small, this affection may be removed by applying a good shielding but it is not ease to remove the affection from a geometrical factor. This affection must be however calculated by the theoretical methods and analytical solution in the equation of these factors. The fundamental purpose of this paper lie in the theoretical calculations and practical measurements of the geometrical factor in the coil systems, finite solenoid, and four point prove. In the heoretical calculations, the geometrical factors in the coil systems were calculated by applying the elliptic functions and in the contact points were calculated by applying the elliptic functions and in the contact points were calculated by applying the eigen functions and the infinite series. The measurements were carried out by using the sensitive electronic device made from author's design, as shown in the Fig. 9. The result of this work has verified the essential correctness of theoretical investigations and measuring techniques of geometrical factors on the design of sensitive electronic devices. It also has several advantages such that: (1) all the data obtained may give effective data to designer to work on the field of sensitive electronic devices or microelectronic devices, (2) it has evidently explained the characteristics of electrical investigations and physical definition, and has removed the conventional error of geometrical factors in the coil systems and contact points.

• Nuclear Engineering and Technology
• /
• 제56권8호
• /
• pp.3335-3346
• /
• 2024

Due to the radiation released by commonly used isotopes, many nuclear, medical, and industrial facilities require proper radiation shielding. In this work, distinct copper borate glasses intercalated with varied aluminum and vanadium oxide (Al₂O₃ and V₂O₅) content have been synthesized and used against radiation (gamma rays and fast/thermal neutrons). The different percents were as follows: [60% B₂O₃ + 35% CuO + (5-x)% Al₂O₃ + xV₂O₅], where x = 0, 1, and 2.5 wt.%, which was coded as BCu(5-x)Al:xV. The synthesized glass samples were characterized using Fourier transforms, infrared, and X-Raydiffraction analysis. Experimentally, the radiation shielding possessions of the samples were established using an HPGe detector at the gamma energy lines 0.356 MeV, 0.661 MeV, 1.173 MeV, and 1.332 MeV. Also, the prepared glasses were investigated theoretically using the Monte Carlo code (MCNP5) at photon energies of 0.015-15 MeV. Also, the fast and thermal neutron macroscopic effective removal cross-sections were calculated using MRCsC and JANIS-4.1 software, respectively. The prepared sample BCu2.5Al:2.5V, which has a vanadium and aluminum content of 2.5%, has the highest linear attenuation coefficient as well as the highest removal cross-section for fast, and thermal neutrons.

• Journal of Radiation Protection and Research
• /
• 제13권2호
• /
• pp.9-20
• /
• 1988

자연 방사선 피폭선량 중 우주선 전리 성분의 기여를 정량하기 위하여 LiF TLD를 이용하여 약 1년반에 걸쳐 3개월 간격의 주기적 측정을 수행하였다. TLD는 세 가지를 사용하였는데 그것은 칩과 PTFE원판형으로 된 두 가지의 $^{7}LiF$와 중성자 성분의 기여를 가려내기 위한 원판형의 $^{6}LiF$였다. 선량 측정은 뱃지에 넣은 TLD를 충남대학교 대덕 캠퍼스의 한4층 콘크리트 건물내 3층의 한 연구실에 설치한 10-15cm 두께의 납차폐 상자에 넣어서 90일 간격으로 다섯주기 동안 수행하였다. 비교 연구를 위하여 3'${\phi}\;{\times}\;3$'원통형NaI(Tl) 섬광 검출기와 1024채널 MCA를 이용하여 3MeV 이상의 우주선 경성분에 대한 분광분석을 병행하였는데 그 결과 옥내 차폐체를 이용한 TLD측정치는 옥외 우주선 전리 성분의 약 75%를 측정하고 있음이 밝혀졌다. 이와 같은 차폐 손실을 보정한 TLD측정 결과에 의하면 충남대 대덕 캠퍼스 옥외에서 우주선 전리 성분의 기여는 $34.3{\pm}1.1nGy-h^{-1}$로 나타났는데 이것은 이 측정 지점에서 예측할 수 있었던 선량 값과 매우 잘 일치하는 것이다.