Development of radiological concentrations and unit liter doses for TWRS FSAR radiological consequence calculations

Radiological consequence assessments using time-varying source terms in ONERS- decision support system for nuclear emergency response

Progress in Nuclear Energy ◽

10.1016/j.pnucene.2020.103436 ◽

2020 ◽

Vol 127 ◽

pp. 103436

Author(s):

S.S. Raja Shekhar ◽

C. Venkata Srinivas ◽

P.T. Rakesh ◽

R. Venkatesan ◽

B. Venkatraman

Keyword(s):

Decision Support ◽

Decision Support System ◽

Emergency Response ◽

Support System ◽

Time Varying ◽

Source Terms ◽

Radiological Consequence ◽

Nuclear Emergency

Download Full-text

Evaluation on Radiological Consequence Induced by MSLB Accident With Alternative Source Term

18th International Conference on Nuclear Engineering: Volume 1 ◽

10.1115/icone18-29615 ◽

2010 ◽

Author(s):

Jingxi Li ◽

Gaofeng Huang ◽

Lili Tong

Keyword(s):

Power Plant ◽

Nuclear Power Plant ◽

Nuclear Power ◽

Power Plants ◽

Nuclear Power Plants ◽

Source Term ◽

Control Room ◽

Power Station ◽

Alternative Source ◽

Radiological Consequence

The major threat that nuclear power plants (NPPs) pose to the safety of the public comes from the large amount radioactive material released during design-basis accidents (DBAs). Additionally, many aspects of Control Room Habitability, Environmental Reports, Facility Siting and Operation derive from the design analyses that incorporated the earlier accident source term and radiological consequence of NPPs. Depending on current applications, majority of Chinese NPPs adopt the method of TID-14844, which uses the whole body and thyroid dose criteria. However, alternative Source Term (AST) are commonly used in AP1000 and some LWRs (such as Beaver Valley Power Station, Units No. 1 and No. 2, Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 And 2, Kewaunee Power Station and so on), so it is attempted to adopt AST in radiological consequence analysis of other nuclear power plants. By introducing and implementing the method of AST defined in RG 1.183 and using integral safety analysis code, a pressurized water reactor (PWR) of 900 MW nuclear power plant analysis model is constructed and the radiological consequence induced by Main Steam Line Break (MSLB) accident is evaluated. For DBA MSLB, the fractions of core inventory are assumed to be in the gap for various radionuclides and then the release from the fuel gap is assumed to occur instantaneously with the onset of assumed damage. According to the assumptions for evaluating the radiological consequences of PWR MSLB, dose calculation methodology is performed with total effective dose equivalent (TEDE) which is the criteria of dose evaluation. Compared with dose criteria of RG 1.183, the dose of control room, exclusion area boundary and outer boundary of low population zone are acceptable.

Download Full-text

Assessment Of Radiological Consequence Of Radioactivity In Monazite Beach Sand In South West Coastal Region In Southern India

Materials Today Proceedings ◽

10.1016/j.matpr.2019.05.159 ◽

2019 ◽

Vol 16 ◽

pp. 784-791

Author(s):

S.R. Soniya ◽

S. Monica ◽

A.K Visnu Prasad ◽

P.J. Jojo

Keyword(s):

Coastal Region ◽

Southern India ◽

Beach Sand ◽

South West ◽

Radiological Consequence

Download Full-text

Preliminary Study of Influence of Severe Accident Mitigation Countermeasures to In-Vessel Release of Fisson Products

18th International Conference on Nuclear Engineering: Volume 2 ◽

10.1115/icone18-29585 ◽

2010 ◽

Author(s):

Gaofeng Huang ◽

Xuewu Cao ◽

Jingxi Li

Keyword(s):

Nuclear Power ◽

Fission Products ◽

Early Time ◽

Severe Accident ◽

Base Case ◽

Primary Loop ◽

Radiological Consequence ◽

Secondary Loop ◽

Station Blackout ◽

Preliminary Study

During the severe accident in a nuclear power plant, large amounts of fission products release with accident progression, which includes in-vessel release and ex-vessel release. Mitigation of release of fission products is the need of alleviating radiological consequence in severe accident. Mitigation countermeasures to in-vessel release of fission products are studied, including feed-bleed in primary loop, feed-bleed in secondary loop and cooling of ex-vessel. Representative high pressure melt accident of station blackout is chosen, and different entry condition of countermeasures is assumed. The results show that: (1) Feed-bleed in primary loop is an effective countermeasure to mitigate in-vessel release of fission products. With early time to implement the countermeasure, in-vessel release fraction of fission products is low. (2) Feed-bleed in secondary loop is also an effective countermeasure to mitigate in-vessel release of fission products. Low in-vessel release fraction of fission products is produced with early time of countermeasure implemented. (3) Cooling of ex-vessel is not an effective countermeasure to control in-vessel release of fission products, the in-vessel release fraction in this case is almost equal to base case that uses none countermeasure.

Download Full-text