Cao Xinrong

U.S.NRC Progress in Source Term Evaluation

In this paper progress in the source term evaluation has been presented. This paper presents the development of Source term evaluation of Nuclear Power Plants (NPPs) for Probabilistic Risk Assessment (PRA) for operation and licensing of the NPPs. Substantial research had been carried out by NRC, for this purpose. Nuclear Research and development (R&D) Agencies like ANL, NEA, ORNL, SNL, BCL and ANS incorporate with U.S. NRC, and by the time they had published research reports on progress in risk assessments and source term evaluation of different accidental consequences in Commercial NPPs.

Scattering of Plane SH-Wave by a Cylindrical Hill of Arbitrary Shape

The problems of scattering of plane SH-wave by a cylindrical hill of arbitrary shape is studied based on the methods of conjunction and division of solution zone. The scattering wave function is given by using the complex variable and conformal mapping methods. The conjunction boundary conditions are satisfied. Furthermore appling orthogonal function expanding technique, the problems can finally be summarized into the solution of a series of infinite algebraic equations. At last, numerical results of surface displacement of a cylindrical arc hill and of a semi-ellipse hill are obtained. And those computational results are compared with the results of finite element method (FEM).

Mitigation of PWR in-containment iodine source term under LOCA

Iodine is one of the most hazardous fission products from radiological consequences of LWR. In this paper, the iodine source term has been evaluated for two-loop PWR under severe accident initiated due LOCA. The TMI-2 reactor is considered as the reference reactor. The modelling and simulations of release of iodine have been carried out by developing a MATLAB code that uses the post-accident conditions and core inventory as its input. The containment response, in order to mitigate the environmental and incontainment iodine source term is studied in normal, emergency, and isolation states of containment. The in-containment iodine source term has been evaluated with, and without operation of Engineering Safety features (ESFs). The environmental iodine source term is calculated as the function of containment response. The containment retention factor (CRF) for iodine has also been studied in all confined states of containment. Results indicate the weak sensitivity of iodine towards exhaust rate with ESFs operation.

US NRC progress in source term evaluation

In this paper progress in the source term evaluation is presented. This paper presents the development of source term evaluation of Nuclear Power Plants (NPPs) for Probabilistic Risk Assessment (PRA) for operation and licensing of the NPPs. Substantial research had been carried out by NRC, for this purpose. Nuclear Research and Development (R&D) agencies like ANL, NEA, ORNL, SNL, BCL and ANS incorporate with US NRC, and have published research reports on progress in risk assessments and source term evaluation of different accidental consequences in commercial NPPs.

Safety Features of a Pressurized Water Reactor Utilizing Coated Fuel Particles With a Novel Composition

In this research paper, a safety analysis has been carried out for the conceptual design of a compact sized pressurized water reactor (PWR) core that utilizes a tristructural-isotropic (TRISO) fuel particle with an inventive composition. The use of TRISO fuel in PWR technology improves integrity of the design due to its fission fragments retention ability, as this fuel provides first retention barrier within the fuel itself against the release fission fragments. Hence, addition of one more reliable barrier in well established PWR technology makes this design concept safer and environment friendly. A small amount of Pu-240 has been added in the fuel for excess reactivity control. This addition of Pu-240 in TRISO fuel reduces the number of burnable poison and control rods required for reactivity control, and completely eliminates the requirement of soluble boron system. The suggested design operates at much lower temperature and pressure than a standard PWR power reactor, and the presence of TRISO fuel ensures the retention of fission fragments at elevated temperatures. All reactivity coefficients were found negative for the designed core, and the shutdown margin has also been increased with the suggested TRISO fuel composition.