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 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
Latest Magazine Issues
Jun 2026
Jan 2026
2026
Latest Journal Issues
Nuclear Science and Engineering
July 2026
Nuclear Technology
June 2026
Fusion Science and Technology
May 2026
Latest News
North American construction is back—smaller and faster—at OPG’s Darlington
“The nuclear renaissance is real here,” said Ontario Power Generation’s Subo Sinnathamby on May 8, one year to the day after OPG secured a final investment decision to build the first of four planned BWRX-300 reactors at its Darlington nuclear power plant, and shortly after the new reactor’s foundation was lifted into place. “We got our license to construct in April and our [final investment decision] in May, and we’ve been off to the races since.”
Maolong Liu, Yuki Ishiwatari, Koji Okamoto
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 216-228
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-57
Articles are hosted by Taylor and Francis Online.
As Units 1, 2, and 3 of the Fukushima Daiichi nuclear power plant (NPP) entered the phase of long-term station blackout following the huge tsunami, the decay heat could not be effectively removed from the reactor vessel and resulted in high in-vessel pressure and temperature. The Tokyo Electric Power Company announced that the safety relief valves of Fukushima Daiichi NPP Unit 1 (1F1) were never manually opened. However, the measured reactor pressure was decreased to ∼1 MPa at 2:43 on March 12, 2011. Such unanticipated depressurization might accelerate core uncovery and on the other hand delay containment failure caused by direct containment heating. In addition, the failure time and the failure path of the boiling water reactor pressure boundary before manual depressurization have a huge impact on the resulting source term. The authors modeled the creep failure of the stainless steel guide tubes of the source range monitor in the core and the main steam line and estimated the possible depressurization mechanism of 1F1 using the SAMPSON (Severe Accident Analysis Code with Mechanistic, Parallelized Simulations Oriented towards Nuclear Field) severe accident analysis code.