| 1. |
|
|
| 2. |
|
|
| 3. |
- Charbord, Jeremie, et al.
(författare)
-
In vivo screen identifies a SIK inhibitor that induces beta cell proliferation through a transient UPR
- 2021
-
Ingår i: Nature Metabolism. - : Springer Science and Business Media LLC. - 2522-5812. ; 3:5, s. 682-700
-
Tidskriftsartikel (refereegranskat)abstract
- It is known that beta cell proliferation expands the beta cell mass during development and under certain hyperglycemic conditions in the adult, a process that may be used for beta cell regeneration in diabetes. Here, through a new high-throughput screen using a luminescence ubiquitination-based cell cycle indicator (LUCCI) in zebrafish, we identify HG-9-91-01 as a driver of proliferation and confirm this effect in mouse and human beta cells. HG-9-91-01 is an inhibitor of salt-inducible kinases (SIKs), and overexpression of Sik1 specifically in beta cells blocks the effect of HG-9-91-01 on beta cell proliferation. Single-cell transcriptomic analyses of mouse beta cells demonstrate that HG-9-91-01 induces a wave of activating transcription factor (ATF)6-dependent unfolded protein response (UPR) before cell cycle entry. Importantly, the UPR wave is not associated with an increase in insulin expression. Additional mechanistic studies indicate that HG-9-91-01 induces multiple signalling effectors downstream of SIK inhibition, including CRTC1, CRTC2, ATF6, IRE1 and mTOR, which integrate to collectively drive beta cell proliferation. A high-throughput chemical screen identifies the salt-inducible kinase inhibitor HG-9-91-01 as a driver of beta cell proliferation, acting through an ATF6-dependent unfolded protein response.
|
|
| 4. |
- Chen, Zhibin, et al.
(författare)
-
Summary of the 3rd International Workshop on Gas-Dynamic Trap based Fusion Neutron Source (GDT-FNS)
- 2022
-
Ingår i: Nuclear Fusion. - : IOP Publishing. - 0029-5515 .- 1741-4326. ; 62:6
-
Tidskriftsartikel (refereegranskat)abstract
- The 3rd International Workshop on Gas-Dynamic Trap-based Fusion Neutron Source (GDT-FNS) was held through the hybrid mode on 13-14 September 2021 in Hefei, China, jointly organized by the Hefei Institutes of Physical Science (HFIPS), Chinese Academy of Sciences (CAS), and the Budker Institute of Nuclear Physics (BINP), Russian Academy of Sciences (RAS). It followed the 1st GDT-FNS Workshop held in November 2018 in Hefei, China, and the 2nd taking place in November 2019 in Novosibirsk, Russian Federation. With the financial support from CAS and China Association for Science and Technology (CAST), this workshop was attended by more than 80 participants representing 20 institutes and universities from seven countries, with oral presentations broadcast via the Zoom conferencing system. Twenty-two presentations were made with topics covering design and key technologies, simulation and experiments, steady-state operation, status of the ALIANCE project, multi applications of neutron sources, and other concepts (Tokamaks, Mirrors, FRC, Plasma Focus, etc). The workshop consensus was made including the establishment of the ALIANCE International Working Group. The next GDT-FNS workshop is planned to be held in May 2022 in Novosibirsk.
|
|
| 5. |
- Chernitskiy, S. V., et al.
(författare)
-
A fuel cycle for minor actinides burning in a stellarator-mirror fusion-fission hybrid
- 2017
-
Ingår i: PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY. - : KHARKOV INST PHYSICS & TECHNOLOGY. - 1562-6016. ; :1, s. 36-39
-
Tidskriftsartikel (refereegranskat)abstract
- The MCNPX Monte-Carlo code has been used to model a concept of a fusion-fission stellarator-mirror hybrid aimed for transmutation transuranic content from the spent nuclear fuel. A fuel cycle for the subcritical fusion-fission hybrid is investigated and discussed.
|
|
| 6. |
- Chernitskiy, S. V., et al.
(författare)
-
Minor actinides burning in a stellarator-mirror fusion-fission hybrid
- 2015
-
Ingår i: Problems of Atomic Science and Technology. - 1562-6016. ; :1, s. 20-23
-
Tidskriftsartikel (refereegranskat)abstract
- The MCNPX Monte-Carlo code has been used to model a compact concept of a fusion-fission reactor based on a combined stellarator-mirror trap for transmutation transuranic elements from the spent nuclear fuel. Calculation results for fission rates for transuranic elements are presented.
|
|
| 7. |
- Chernitskiy, S. V., et al.
(författare)
-
Neutronic Model Of A Fusion Neutron Source
- 2013
-
Ingår i: Problems of Atomic Science and Technology. - 1562-6016. ; :1, s. 61-63
-
Tidskriftsartikel (refereegranskat)abstract
- The MCNPX numerical code has been used to model a fusion neutron source based on a combined stellarator-mirror trap. Calculation results for the neutron spectrum near the inner wall and radial leakage of neutrons through the mantle surface of the fusion neutron source are presented.
|
|
| 8. |
- Chernitskiy, S. V., et al.
(författare)
-
Neutronic Model of a Stellarator-Mirror Fusion-Fission Hybrid
- 2012
-
Ingår i: PROBL ATOM SCI TECH. - 1562-6016. ; :6, s. 58-60
-
Tidskriftsartikel (refereegranskat)abstract
- The MCNPX numerical code has been used to model a compact concept for a fusion-fission reactor based on a combined stellarator-mirror trap. Calculation results for the radial leakage of neutrons through the mantle surface of the fission reactor are presented.
|
|
| 9. |
- Chernitskiy, S. V., et al.
(författare)
-
Neutronic Model of a Stellarator-Mirror Fusion-Fission Hybrid
- 2013
-
Ingår i: Fusion science and technology. - 1536-1055 .- 1943-7641. ; 63:1T, s. 322-324
-
Tidskriftsartikel (refereegranskat)abstract
- The MCNPX numerical code has been used to model the neutron transport in a mirror based fusion-fission reactor. The purpose is to find a principal design of the fission mantle which fits to the neutron source and to calculate the leakage of neutrons through the mantle surface of the fission reactor. The fission reactor part has a cylindrical shape with an outer radius 1.66 m and a 4 m length. The fuel has the isotopic composition of the spent nuclear fuel from PWR after uranium-238 removal. Inside the fission reactor core is a vacuum chamber with a radius 0.5 m containing a 4 m long hot plasma producing fusion neutrons. To sustain the hot ion plasma which is responsible for the fusion neutron production, neutral beam injection is considered. Calculation results for the radial leakage of neutrons through the mantle surface of the fission reactor are presented. These calculations predict that the power released with neutrons from the reactor to outer space would be small and will not exceed the value of 6 kW while the reactor thermal power is 1 GWth.
|
|
| 10. |
- Chernitskiy, S. V., et al.
(författare)
-
Static Neutronic Calculation of a Fusion Neutron Source
- 2014
-
Ingår i: Problems of Atomic Science and Technology. - 1562-6016. ; :6, s. 12-15
-
Tidskriftsartikel (refereegranskat)abstract
- The MCNPX numerical code has been used to model a fusion neutron source based on a combined stellarator-mirror trap. Calculation results for the neutron flux and spectrum inside the first wall are presented. Heat load and irradiation damage on the first wall are calculated.
|
|
