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
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
April 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
DOE launches UPRISE to boost nuclear capacity
The Department of Energy’s Office of Nuclear Energy has launched a new initiative to meet the government’s goal of increasing U.S. nuclear energy capacity by boosting the power output of existing nuclear reactors through uprates and restarts and by completing stalled reactor projects.
UPRISE, the Utility Power Reactor Incremental Scaling Effort, managed by Idaho National Laboratory, is to “deliver immediate results that will accelerate nuclear power growth and foster innovation to address the nation’s urgent energy needs,” DOE-NE said in its announcement.
Kirill Fedorovich Raskach
Nuclear Science and Engineering | Volume 165 | Number 3 | July 2010 | Pages 320-330
Technical Paper | doi.org/10.13182/NSE09-47
Articles are hosted by Taylor and Francis Online.
The differential operator method is an effective Monte Carlo technique developed for calculating derivatives and perturbations. It has often been applied to eigenvalue problems. This paper extends applicability of the method to inhomogeneous problems with internal and external neutron sources. Two issues associated with these problems were considered. First of all, it was necessary to use a special technique that treats inhomogeneous problems within the framework of the neutron generation method with a constant number of neutrons per generation. This technique optimizes Monte Carlo calculations and eliminates difficulties that appear in the classical technique as the effective multiplication factor approaches unity. Furthermore, use of the technique facilitated solving the usual issue of the differential operator method associated with fission source, or more exactly total neutron source, perturbations because some modification of the approach recently proposed for eigenvalue problems could be employed. The proposed technique can be used for calculating derivatives of reaction rates with respect to neutron cross sections or material densities. Perturbations of external source and geometrical parameters were outside the scope of this work.