Write a 2 page essay describing how business decision support systems have evolved over the past several decades as computer and data capabilities have grown. The rubric for this assignment can be viewed when clicking on the assignment link.

Surname 1

Name:

Instructor:

Course:

Date:

Safety in the Nuclear Industry

QUESTION 1A

Ref. Control Type of control Rank

A Each batch of

enriched uranium

must not exceed a

net uranium-235

mass of 600g.

PASSIVE ENGINEERED SAFETY FEATURE-It is

universally accepted that nuclear energy is

responsible for approximately 15% of the global

electricity (Mario, et al 1260). In this case, so many

nations are in the process of introducing nuclear

energy or grow their overall nuclear

energy .Additionally, ever since the beginning of the

1980s, it known that the application of passive

engineered safety features or rather those systems

whose overall operation takes full advantage of

convention and gravity natural forces, can either

directly or indirectly play a very crucial role in

making the economics of nuclear energy more

simplified and potentially improve the dynamics of

nuclear power plant designs. For instance the

Conference that revolved around the Safety of

1

Surname 2

Nuclear Power that was basically convened in the

year 1991 argued that the employment of passive

safety measures is very effective and desirable in

realizing simplification and improving performance

reliability of the effective and essential safety

functions and for this case, it should be used

wherever necessary

B The uranium-235

concentration in the

dissolver must be

monitored by regular

sampling and must

not be allowed to

exceed

10 gU235/litre.

ACTIVE ENGINEERED “SAFETY

MECHANISM”- One major difference between

active engineered safety mechanism and passive

safety feature is the fact that active safety depends

on a computer automated intervention or an operator

whereas on the other hand, passive safety

mechanisms depends basically on natural selection

or rather the laws of nature in ensuring that the

reactor adjusts automatically on adverse events in a

very effective manner (Mario, et al 1260).

Additionally, this systems mechanisms are activated

automatically in response to any accident or safety

concern or any related abnormal event .besides, in a

nuclear reactor, such mechanism are activated with

3

Surname 3

the help of a human operator, mechanically or

automatically with the help of a computer driven

systems.

C The total quantity of

liquor in the

dissolver must be

monitored and

automatically

controlled as not to

exceed a maximum

of 10 litres.

ACTIVE ENGINEERED “SAFETY

MECHANISM”- Active engineered systems

mechanisms are basically the system mechanisms

that employ the active understanding of the nuclear

dissolver vessel in ensuring that the nuclear reactor

is working in a more effective way (Mario, et al

1260). In other words, this system mechanism takes

into consideration the nuclear stability control

systems, traction control systems.

4

D The dissolver vessel

should be designed

to be safe by

diameter for all

possible uranium

enrichments and

concentrations.

Operational controls “operating instructions”- In the

implementation of safety in the nuclear reactor

dissolver, consideration should also be given to the

type and quality of information provided by each

operational indicator. In other words, it is accepted

that there is a direct relationship when it comes to

the safety and the indicator

7

E The dissolver vessel

should be fitted with

Operational controls “operating instructions”- ,

indicators are operational indicators should not be

5

Surname 4

fixed neutron

poisons so that

criticality safety will

be ensured for all

possible uranium

enrichments and

concentrations.

susceptible to any kind of manipulation and the

indicators should not be expressed in quantitative

terms accepted as unambiguous

F Batches of

gadolinium should

be added to each

batch of uranium to

ensure that the

dissolver product

will be safe under all

possible conditions.

Passive engineered-safety feature”- Some new

passive engineered designs fundamentally utilize

natural selection basically as a technique of

eliminating core power in normal nuclear energy

operations. However, the employment of passive

engineered systems help in the elimination of costs

that revolve around maintenance, operation,

installation of active features that need several

pumps with redundant and independent electric

power supplies. On the contrary, taking into account

the weak driving forces associated with this kind of

safety features based on natural circulation, analysis

methods and careful designs must be used so as to

see to it that the passive engineered safety measures

focus only on their intended purpose. For instance,

for thermal insulation purposes, the size and the type

2

Surname 5

of the insulation used in the reactor will be basically

be predominantly reflective metallic. besides, any

other fibrous insulation methods employed in the

nuclear energy reactor should be basically be

conformance with the nuclear reactors’ RG 1.36 as

far as the leachable concentration of enriched

uranium oxide in nitric acid. Passive nuclear safety

is universally accepted as a nuclear reactor feature

that does not need any operator to shut it down in

case of an emergency which in most cases results

from overheating due to loss of coolant flow or loss

of coolant. One reason why this safety feature is

important in enriched uranium oxide in nitric acid

nuclear creator is based on the fact that their basic

physics law tend to slow rather than increasing

because of their tendency to rely ion engineering of

components. Therefore, given the nature of its

operation in the dissolver vessel, then it is one of the

best safety measures.

G The dissolver vessel

should be designed

Operational controls “Operating Instructions”-in this

case, the nuclear reactor organization needs to set up

6

Surname 6

with a maximum

volume of 10 litres.

appropriate arrangements that will see to it that the

nuclear reaction minimizes the risks to health and

safety. Hence the volume of the nuclear reactor

should as well be conducted based on the quality

assurance of the organization and the dissolver

vessel quality.

QUESTION 1B

Table 1b (Question 1b)

Ref. Control Type of control Rank

A Only paint tins with a

gross mass of less than

10kg may be admitted

to the store.

PASSIVE ENGINEERED SAFETY FEATURE-

When this remotely actuated makeup safety feature

is implemented effectively, it will ensure the

adequacy of uranium bearing sludge. Storage and

in the process, it will help in the protection of the

safety and human health in case of any accident

conditions. Besides, if this storage safety feature is

demonstrated to be reliable, it is universally

accepted that it will ensure that the decomposition

coolant reactor is just below the normal weight of

1

Surname 7

the uranium bearing sludge that can be supported

effectively by the nuclear reactor.

B Operators must ensure

that the edge to edge

separation between

paint tins in the store

is not less than 60cm.

Active engineered “safety mechanism”-this safety

mechanism is very approximate because in this

case, it is assumed that the maximum gradients for

each recovered sludge, each wall and the reactor

floor occur simultaneously. Apparently as a result

of their differing strengths then then will basically

heat up and decompose at different rates.

Moreover, another reason is because there are

doubts about the extent to which the nuclear

decomposer structure will be capable of resisting

the thrusts generated by the recovered sludge and

the steel liner. In this case, the estimated thickness

measurers at a number of cross-sections are an

evidence of the strength of the recovered sludge,

the comprehensive strength of the decomposition

sludge and the sections dimensions.

3

C Paint tins must not be

stacked on top of each

other.

OPERATIONAL CONTROLS “operation

measures”-stacking tins on top of each other may

cause adverse conditions as far as changes and

modifications in properties that may result from

loss of material. In other words, the operational

5

Surname 8

effectiveness when it comes to storage of

recovered sludge depends on the uniqueness of its

content and therefore, it should not be ambiguous

in any state.in some case, protective steel are

embedded in the spaces between the stacks as well

as the equipment situated inside the nuclear reactor

container.

D A grid of 60cm

squares must be

marked on the floor

area of the store. Each

grid square may hold

only a single paint tin,

which must be placed

at the centre of the

square.

Operational controls (Control measures) - this is a

control measure that will ensure that the recovered

sludge is arranged in a very organized manner. In

this case, the nuclear reactor will be able to detect

the nature of human error during operations.

6

E A wooden framework

will be provided to

provide a series of

defined storage

locations for the paint

tins awaiting assay.

Paint tins may only be

Passive engineered “safety feature”-Employment

of a wooden framework will ensure that the

recovered sludge decompose through natural

selection or the forces of gravity. In this case, The

framework or rather the containment design will

ensure that the nuclear reactor decomposition curb

the uncontrolled release of sludge and radioactivity

4

Surname 9

stored in these

designated locations.

to the neighbouring environment hence to some

extent, it acts as a safety feature to human health.

F The paint tins to be

used must have a

volume of 10 litres.

Operations control “Control measures”-because

the primary purpose of the tins is to basically

control the adverse effects of the recovered sludge

due to pressure differences, therefore, it is obvious

that since the pressure in the nuclear reactor

coolant is very high, the volume or rather the

capacity of the tins should as well be very high

(Herrero, and Otero 1237). Therefore, the 10 litre

tins should be very helpful in controlling any cases

of flooding because of sludge overflows.

2

Question 2

A very good nuclear health and safety culture is universally accepted to possess the

following attributes: First, whenever there is any possible adverse case, Quality, and safety are

given priority over cost and schedule (David J., et al 233). In other words, any potential errors

and near misses whenever they occur are basically viewed as an issue of concern that can be as

well be taken to be a learning experience that can later generate benefits to the nuclear plant. In

simple terms, individuals are therefore encouraged to report, identify and correct any form of

imperfections so as to ensure that any individual attached to the nuclear plant to avert any future

problems (Mariscal, Herrero, and Otero 1237). Moreover, every change that occur in the nuclear

Commented [U1]: *What are the 3 key safety characteristics unique to the nuclear industry that need to be managed? This part was not answered. Please introduce the 3 key safety characteristics unique to the nuclear industry? And then show how they’re managed. What stated in the Draft is NOT unique to the Nuclear industry and is applicable in any process industry? Please rectify. Looked at functionally, the three basic safety functions in a nuclear reactor are: •to control reactivity, •to cool the fuel and •to contain radioactive substances.

See Ref/http://www.world-nuclear.org/information- library/safety-and-security/safety-of-plants/safety-of- nuclear-power-reactors.aspx

Surname 10

plant, every safety assessment and every plant meeting should be considered as an opportunity to

learn, reinforce and tech the preceding principles and attributes (David. et al 255). Besides, this

can only be realized if the nuclear reactor plant management prevent isolationism or

individualism and in the process, help in the establishment of a learning organization.

Second, the nuclear plant activities should be carried out based on the energy plant

procedures. In other words, if any individual has any doubts as far as the procedure is concerned,

the plant evolution is stopped by ensuring that the nuclear reactor plant is returned is to its initial

stable and safe condition.in such circumstances, the procedures are changed and evaluated if

need be before moving to the next stage (Mariscal, `Herrero, and Otero 1237). Besides, if

problems are identified, the root cause of the devastating effect is the root cause and in the

process establishing the best solutions without necessarily being diverted by who contributed or

identified the devastating effect or who contributed to the challenging problem. In such

instances, the primary goal is to see what is right and not basically who is right.

Third, the main primary objective of supervisory management revolves around the fact

that each nuclear plant task is performed in a very effective manner the first time (Alberto and

Ketokivi 66). Additionally, the management or the supervisory should be able to accept full

responsibility for each and every happening and the success of each work and be involved in the

work in every possible manner that will ensure that the work is successfully (Herrero, and Otero

1237). Moreover, the supervisors should as well establish policies and practices that convey an

overall nuclear plant’s attitude of individual trust and in the process, set up measures that can be

able to foster teamwork at each and every organizations level and in the process, reinforce

positive working attitude towards safety and health (Mario, et al 1260).

Surname 11

Furthermore, feedback should be solicited from each and every organization personnel to

assist in establishing impediments, concerns and any opportunities to improve on the level of

organizational safety. In simple terms, this is achieved whenever the management encourages

and reinforces a collective behavior that reinforces and leads the plant staff to identify any

potential problems fully and promptly. Therefore, the nuclear plant as an organization possesses

an obligation and a commitment to improve the safety and health continuously and in the

process, help in managing any form of change effectively.

QUESTION 3

ALARP is universally accepted as an aspect of reducing the level of risks in such a way

that it is very practically low (As Low As Reasonably Practicable). Additionally, the operator in

practice must be in a position to portray through supported and reasoned arguments that in the

operation, there are no any other options that can be adopted reasonably tom curb the risk level

to a much lower level (Knut 235). Reasonably practicable in this case is used to represent a much

narrower terminology as compared to physically possible. In other words this can be assumed

that the amount of risk is weighed upon the placement of the sacrifices involved in curbing the

risk whether it is time, trouble, or money. If there will be any gross disproportion between the

two scales the risk being found to be insignificant then the defendants is able to discharge the

onus on the two calculated options (Prasad, Cole and Haase).

Any safety case is supposed to show how its operator will be able to meet the regulatory

provisions requirements that are very relevant to the control of any adverse effects including

risks top health and safety of its personnel at the facility (Alan, et al 453). Most of the legal

regulations are embedded in the terminology or rather the phrase that revolve around curbing the

risk level to ALARP. In this case, it is accepted that the operator must work hard to prove via

Surname 12

supported and reasoned arguments that indeed there are no any other measures or techniques that

can practically be employed to make the risks to be as low as possible further (Prasad, 213).

Additionally, the phrase reasonably practicable is very significant to the health and safety of any

nuclear energy regime (Barnard, et al 265). In other words, it gives room to the operator to

establish goals to ensure their own safety rather than depending and following blindly

prescriptive requirements. Besides, such conditions also allow the nuclear plant to either accept

or reject any arrangements of the operator as far as safety is concerned. Furthermore, this act of

flexibility in any nuclear plant can be very beneficial but it can at times be very challenging

because it basically needs individuals to practice judgment with respect to how they will be able

to curb any potential risks (Barnard, et al 270). One striking aspect in this case is the fact that a

decision can be reached upon evaluation of any existing good practice. However, in case the

nuclear plant incurs a complex situation, it is accepted that it can be very challenging to make a

decision based on good practice alone. For example, in case the nuclear plant has embraced a

new technology, then it can be very challenging to make a decision following previous good

practice hence leaving room for other decision-making techniques to be employed in informing

the judgment.

The safety case for any nuclear plant must possess a detailed description of the legal

formal assessment of safety that is worked on by the operator. In such instance, the regulations of

the FSA should identify all potential adverse happenings that might cause a major accident.

Besides, the FSA should also identify control measures and technical measures that are important

in reducing any potential risks to a level that can be classified to be ALARP. In other words,

ALARP can basically be classified, as a very reasonable way that any nuclear plant can approach

any adverse effects or potential problems since it acknowledges that there is no organization that

Surname 13

can realize 100% absolute safety which makes an essential part of legislative goal setting.

Moreover, the adopted control measures in ALARP for any primary adverse event can be taken

to collectively eliminate the risk to a level that can be deemed to be ALARP. Thus basically

implies that, it is only the inclusion of sufficient level of related risk information will some

nuclear plants be able to make the right decision as far as the appropriate safety and health

measure is concerned.

When it comes to legacy facilities, the extent of reasonable practicability revolves around

whether the potential risks that are anticipated can be reduced based on previous good practice.

In this case, the risk assessment is performed by taking into consideration some of the previous

held legal principles and good practice that entailed very low sacrifices. In this case, the higher

the original level of risks in question, the more extensive is the effort involved in showing that

the employment of the good practice will help curb the risk to ALARP. On the other hand, for

new facilities, a selection between multiple fields is encouraged at any stage including the design

stage that revolve around making a decision as far as the design concepts are concerned.

However, in such instances, it is accepted that anew installation has no potential of producing

risk or a problem that is much extensive than the already existing good practice cannot handle for

comparable functions. In other words, in case of anew project, it is wise for the operators to take

into consideration the risks and adverse conditions that are involved over the whole project life

cycle. Therefore, the reasonable risk applicability should therefore be determined based on the

assumptions of this baseline hence ensuring that the risk reduction technique that is chosen is

very ALARP.

Question 4

Commented [U2]: Question 4 part (a): No answer was found for this part of the question [Describe the principal reactions within a reactor core ]!! please consider adding an appropriate answer to this part of the question?? DISCRIB WHAT REACTIONS (EXOTHERMIC REACTIONS) TAKE PLACE INSIDE THE REACTOR CORE? THEN, PRESENT THE SHIELDING MEASURES FOR THE PROCESS.

Surname 14

Radiation protection is universally accepted as a science of protecting the environment

from the adverse influence and implications of ionizing radiation. Additionally, it is a very

extensive issue not only in nuclear energy plants but as well as in medical centers and industries.

Some of the ways in which individuals are protected from ionizing radiation ids through. First,

reducing the time because the a level of radiation an individual is exposed to basically depends

on the time that the individual are directly exposed to the radiation source hence this can be

curbed by reducing the exposure time (Barnard, et al 268). Second, by reducing the distance such

that if an individual is very near the source of radiation then they are believed to be very

vulnerable as compared to if they are very far (Herrero, and Otero 1237). Third is shielding such

that if the source of radiation is very intensive such that distance and time cannot deal with it,

shielding is found to be very efficient. In this case, shielding is made up of concrete, water, or

lead barriers. In case of gamma radiation, it is accepted that depleted uranium can be employed

as a potential shield protection but is found to be inadequate when it comes to shielding of

neutron radiation. The primary source of nuclear radiation in nuclear plants is the nuclear reactor

core and the nuclear reactor itself (Barnard, et al 268). Hence in such instances, the nuclear

shielding employed is biological shielding. Additionally, radiation shields are employed in this

case in reducing neutrons or gamma rays on the reactor vessels. In so doing, this shielding

protects the reactor vessels alongside its internal parts from intensive heat caused by gamma ray

absorption using thermal shields.

A strange gamma and neutron radiation is sometimes employed in protecting the reactor

vessel most especially when it comes to PWR nuclear power plants. Additionally, structural

materials that involve reactor internals and pressure vessels are destroyed by fast neutrons

(Herrero, and Otero 1237). One sure thing is the fact that fast neutrons are responsible in

Surname 15

establishment of structural defects that result into embrittlement of material that are embedded in

the pressure vessel. In this case, in order tom reduce the neutron flux level that occurs at the

vessel level, the core loading strategy can undergo some modifications (Barnard, et al 268). To

curb this issue, out-in fuel loading technique fresh fuel assemblies are employed and placed at

the core periphery. In nuclear plants, one challenging aspect is to shield neutrons and gamma

rays owing to the fact that the ranges of charged particles like alpha-particles and beta-particles

as far as matter is concerned are basically very short.

4b) determination of photon flux

Given mass= 70kg

Projected area= 0.7m2

Depth=0.20m

Linear energy absorption coefficient = 7 m-1

Given the fact that the SI diode thickness is 20 microns, energy is 7 Kev, diode current 1.0 and

assuming the thickness of Al filter =0.20 microns surface area or rather the distance travelled is

0.20 mm, the calculated photon flux is 9.131933045233797 multiplied by 10^12 photons per

second.

4c) Shielding to decrease outside radiation hazard is performed when increasing distance or

decreasing the time is not possible. The material to be used in shielding depends on the kind of

energy and type of radiation. Particles of Alpha are shielded easily. Thin pieces of papers are

enough to stop the alpha particles; hence alpha particles present no outside radiation hazard.

Particles of beta are more penetrating as compared to alpha particles. The shields for beta are

made of brass, aluminum, plastic, or any other materials that possess low atomic number.

Commented [U3]: Please provide the reference of this equation

Commented [U4]: Explain the results determined and state what does the calculated value mean in this context. Please rectify

Surname 16

Material

Linear energy

absorption

coefficient

(cm2/g)

Density

(g/cm3)

Linear energy

abs. coeff.

(m-1)

Water 4.942E-02 1.000E+00 4.94

Concrete 4.557E-02 2.300E+00 1.978

Lead 4.606E-02 1.135E+01 4.058

Iron 4.265E-02 7.874E+00 0.542

Glass 4.447E-02 2.230E+00 1.994

C2) the best material to help reduce the implication of gamma is lead because it has a lower

density and very high absorption rate. Besides, since the linear energy absorption coefficient is

bigger compared to other materials, lead is much better..

4d)

Control Principle Description

Commented [U5]: Relate and refer the determined answer to the concept of ALARP by including a connection statement between the result found and ALARP concept. And consider what so called Cost Benefit Analysis and economical decision making? is lead available and economical?

Surname 17

Reduce

exposure time

the radiation

amount which an

individual

accumulates

depends on the

time they stay in

the field of

radiation

To reduce an individual’s dose, it is advisable to restrict

the time of exposure in the area.in other words, how long

an individual stays in a radiation area is computed based

on limit/dose rate.

Reduce the

exposure

distance

The amount of

gamma radiation

an individual is

exposed to

depends on the

proximity to the

gamma radiation

source.

The intensity of gamma radiation decreases as the

distance between the gamma radiation source and an

i9ndividual decreases.

Lead shielding

Shielding is a

more effective

technique when

employed in

areas where time

and distance are

not able to

Lead is a very common and effective shielding material

because it is inexpensive, it possesses a very high

density, and it is very cheap to work with. However, the

intensity and the amount of shielding employed is

believed to depend on the level and the amount of

photon energy

Surname 18

reduce the

gamma radiation

exposure.

Employment

of a half value

layer

Shows how best

a material is able

to reduce the

intensity of

radiation half as

low as its

original

intensity.

The higher the thickness of a material is able to reduce

the radiation exposure, the more effective it is as far as

reducing the halfway radiation exposure reduction is

concerned (Barnard, et al 268).

Surname 19

Works Cited

Barnard, S., et al. "The first gamma-H2AX bio dosimetry intercomparison exercises of the

w2434developing European biodosimetry network RENEB." Radiation protection

dosimetry 164.3 (2015): 265-270.

Birnbach, David J., et al. "A framework for patient safety: A defense nuclear industry-based

high-reliability model." Joint Commission Journal on Quality and Patient Safety 39

(2013): 233-240.

Hernansanz, Alberto, and Mikko Ketokivi. "Getting to the Core of Matter: The Outsourcing

Hazard in the Nuclear Industry." Academy of Management Proceedings. Vol. 2013. No.

1. Academy of Management, 2013.

Mariscal, M. A., S. García Herrero, and A. Toca Otero. "Assessing safety culture in the Spanish

nuclear industry through the use of working groups." Safety science 50.5 (2012): 1237-

1246.

Martin, Alan, et al. An Introduction to Radiation Protection 6E. CRC Press, 2012.

Martínez‐Córcoles, Mario, et al. "Strengthening Safety Compliance in Nuclear Power

Operations: A Role‐Based Approach." Risk Analysis 34.7 (2014): 1257-1269.

Prasad, K. N. "Rationale for using multiple antioxidants in protecting humans against low doses

of ionizing radiation." The British journal of radiology (2014).

Prasad, K. N., W. C. Cole, and G. M. Haase. "Radiation protection in humans: extending the

concept of as low as reasonably achievable (ALARA) from dose to biological damage."

The British Journal of Radiology (2014).

Surname 20

Ringen, Knut. "Optimal Safety and Health Management of Construction Activities: Evidence

from the US Nuclear Power Industry." 30th International Congress on Occupational

Health (March 18-23, 2012). Icoh, 2012.

Schneider, Mycle, and Antony Froggatt. "World nuclear industry status report 2013." (2013).