Response of six neutron survey meters in mixed fields of fast and thermal neutrons

Kim, S. I.; Kim, B. H.; Chang, Insu; Lee, J. I.; Kim, J. L.; Pradhan, A.S.

doi:10.1093/rpd/nct103

Cited by 8 publications

(2 citation statements)

References 9 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Thermal neutron reference facility is of great significance in many aspects, e.g. calibration of thermal neutron detectors [3] and dose-equivalent meters [4], evaluation of thermal neutron protective materials [5], and neutron activation analysis [6]. A well-characterized thermal neutron field is necessary for researchers and metrologists to make more accurate and reliable measurements.…”

Section: Introductionmentioning

confidence: 99%

Thermal neutron reference radiation facility with high thermalization and large uniformity area

Wang,

Yang,

et al. 2023

Metrologia

View full text Add to dashboard Cite

A new thermal neutron facility based on 12 241Am-Be neutron sources has been established at the National Institute of Metrology, China. It has two independent irradiation fields, the Inner field and Outer field, constructed with high-purity graphite and heavy water as moderators, respectively. Three innovative designs, including the reflection cavity, reflection layer, and homogenizing lens, were introduced to improve the performance of the facility. The reflection layer can increase the thermal neutron fluence rate by about 3~4 times, the reflection cavity also enhances thermal fluence by 3~4 times by taking advantage of multiple scattering of neutrons, and the homogenizing lens mounted on the neutron exit surface of the moderator improve the distribution of thermal neutron. The characteristics of the two fields were investigated by Monte Carlo simulations and experimental measurements. The results show that the new facility has high thermalization and large uniformity area with these innovative designs. For the Inner field, the thermal neutron fluence rate at the reference position is (21433.3 ± 407.2) cm−2∙s−1, the cadmium ratio is 20.6, the nonuniformity is 0.1% over the 40 cm × 40 cm region. For the Outer field, the thermal fluence rate at the reference position is (2046.0 ± 49.1) cm−2∙s−1, the cadmium ratio is 1433, and the nonuniformity is 0.7% in the 70 cm × 70 cm region. The facility is expected to be suitable for the large-size detector, and its excellent performance is attractive for various thermal neutron experiments.

show abstract

Section: Introductionmentioning

confidence: 99%

Thermal neutron reference radiation facility with high thermalization and large uniformity area

Wang,

Yang,

et al. 2023

Metrologia

View full text Add to dashboard Cite

show abstract

“…A very interesting work by Kim et al [16] compares six commercial rem-meters, Berthold LB6411, FHT762 WENDI-2, NRD-9, SNOOPY NP-2, DINEUTRON, and REM-500, and gives evidence of substantial dose underestimation for neutron energies in the 10 MeV region.…”

Section: Introductionmentioning

confidence: 99%

Simplified Approach for Preliminary Evaluation of Effective Dose Rates for Field Applications of D-T Neutron Generators

Contessa¹,

Cherubini²,

Gandolfo³

et al. 2021

IJSSE

View full text Add to dashboard Cite

Portable neutron generators are one of the most widespread sources of fast neutrons for different applications, from activation analysis to quantitative estimation of fissile and fertile materials in radioactive waste packages. New techniques based on these devices have been developed for homeland security, e.g. neutron interrogations of packages suspected of containing substances such as explosives. When using portable generators determination of radiation protection quantities is affected by a series of boundary conditions that could differ from an experimental set-up to another, and Radiation Protection Experts cannot assess operator exposure without the aid of time-expensive Monte Carlo simulations. As it is impossible to foresee all kind of scenarios involving such applications, and time is often a critical variable, safety assessment requires faster, even if less accurate, tools for exposure evaluation. In this article experimental measurements of dose rates in a real scenario involving a D-T neutron generator are considered, to validate the Monte Carlo model developed. Consequently, it was possible to demonstrate that the calibration factor at 14 MeV for a neutron dosimeter provides conservative dose estimates and to propose a stand-alone, fast, and easy-to-use calculation tool which is usable on field by the Radiation Protection Expert without full Monte Carlo calculations.

show abstract

Evaluation of neutron and gamma dose in a new deuterium-deuterium fusion neutron generator facility using MCNP and experimental methods

Bergaoui

Reguigui

Brown

et al. 2019

Applied Radiation and Isotopes

View full text Add to dashboard Cite

Response of six neutron survey meters in mixed fields of fast and thermal neutrons

Cited by 8 publications

References 9 publications

Thermal neutron reference radiation facility with high thermalization and large uniformity area

Thermal neutron reference radiation facility with high thermalization and large uniformity area

Simplified Approach for Preliminary Evaluation of Effective Dose Rates for Field Applications of D-T Neutron Generators

Evaluation of neutron and gamma dose in a new deuterium-deuterium fusion neutron generator facility using MCNP and experimental methods

Contact Info

Product

Resources

About