ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
January 2026
Latest News
Hanford begins removing waste from 24th single-shell tank
The Department of Energy’s Office of Environmental Management said crews at the Hanford Site near Richland, Wash., have started retrieving radioactive waste from Tank A-106, a 1-million-gallon underground storage tank built in the 1950s.
Tank A-106 will be the 24th single-shell tank that crews have cleaned out at Hanford, which is home to 177 underground waste storage tanks: 149 single-shell tanks and 28 double-shell tanks. Ranging from 55,000 gallons to more than 1 million gallons in capacity, the tanks hold around 56 million gallons of chemical and radioactive waste resulting from plutonium production at the site.
Woosong Kim, Kyunghoon Lee, Yonghee Kim
Nuclear Science and Engineering | Volume 192 | Number 1 | October 2018 | Pages 1-20
Technical Paper | doi.org/10.1080/00295639.2018.1497396
Articles are hosted by Taylor and Francis Online.
The Albedo-corrected Parameterized Equivalence Constants (APEC) method, a new leakage correction method for two-group nodal analysis of light water reactors, has been extended to discontinuity factor (DF) correction. First, the error of nodal calculations induced by an inaccurate assembly discontinuity factor (ADF) is evaluated using the reference two-group cross section (XS) and DF calculated from heterogeneous core transport calculations. Functionalization of DF is performed by finding relationships between surfacewise current-to-flux ratio and change of DF from ADF. The least-squares method is used to fit several candidate functions to various core calculation results. The coefficients of APEC XS and DF correction functions are determined considering several color-set models. In this work, the two-dimensional method of characteristics–based lattice code DeCART2D is used for reference core calculations and lattice calculations. The extended APEC method is implemented in an in-house NEM nodal code using the partial-current coarse mesh finite difference acceleration. A small modular reactor (SMR) initial core benchmark is analyzed to evaluate the performance of the extended APEC method. In addition, the extended APEC method is applied to several variants of the SMR core and large variants to assess its general applicability.